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264 documents found
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About the behavior of Zirconium hydride solid bodies under reactor irradiation Ueber das Verhalten von Zirkonhydridmassivkoerpern unter Reaktorbestrahlung
Greiner, L.;Paetz, P.;Staubwasser, WINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--35 - German - 1965
Abstract: This report documents the irradiation of Zirconium hydride samples produced by INTERATOM in the GETR of the General Electric Company. The material had the form of discs and cylinders and was irradiated with a neutron fluence of 1021 nvt (En
Key words: getr reactor;irradiation;knk-2 reactor;metallography;microhardness;microstructure;moderators;neutron fluence;radiation effects;temperature range 0400-1000 k;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087401.pdf
SNEAK-4, a series of physics experiments for KNK II
Engelmann, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK--1022 - English - 1969
Abstract: At the end of 1968 a three months program of neutron physics experiments was performed at SNEAK for the investigation of some nuclear properties of the KNK II reactor. The experiments were conducted by the Karlsruhe Nuclear Research Center in close cooperation with INTERATOM. The results of the measurements on SNEAK assemblies 4A and 4B are reported and compared with calculations. The experimental results of critical mass and reactivities, control rod worths, Doppler coefficient and power distribution were used to draw conclusions for the KNK II design
Key words: comparative evaluations;control rod worths;critical mass;doppler effect;experimental data;fuel assemblies;knk-2 reactor;power distribution;reactivity coefficients;reactor physics;sneak reactor;theoretical data
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087738.pdf
Development work for the moderator of the ITR-fuel Entwicklungsarbeiten zum ITR-Brennstoff-Moderator
Duenner, P.;Becker, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--73.42 - German - 1973
Abstract: In the frame of the ITR-project (Incore-Thermionic-Reactor) fuel-moderator-materials had been investigated, which are also of interest for the KNK-project and which are therefore documented in this report. Partial pressure measurements on the systems Zr-H, Zr U-H, Y-H and YH-H revealed the premise for the elaboration of a hydration technique. On the basis of the functional relation between partial H2-pressure, temperature and H2-content of the hydride, an optimum hydration kinetic for the production of flawless and well defined hydrated Zirconium hydride/Uranium pellets and of Zirconium hydride and Yttrium hydride moderator bodies was developed. Alternatively to the ZrHx-U-technology a powder- metallurgical procedure for the production of a Y-U sinter-alloy as base material was tested. In an irradiation experiment in the DIDO reactor (in Juelich) the burnup behavior of Zirconium hydride-Uranium and Yttrium hydride-Uranium under ITR-similar conditions has been tested. With a U235-burnup of 6.75 % and an irradiation temperature of 490 deg C a fission gas release rate of 0.1 % was observed. The ZrHx-pellets remained mechanically intact, whereas the YHx-pellets crumbled during the post-examinations. The ZrHx-U showed a maximum density reduction of 4.2 %
Key words: burnup;dido reactor;fission product release;fuel pellets;hydration;irradiation;knk-2 reactor;materials testing;thermionic reactors;uranium;yttrium hydrides;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087419.pdf
Diverse shutdown systems for the KNK-1, KNK-2, and SNR-300 reactors
Morgenstern, F.H.;Buchholz, H.;Krueger, H.;Roehrs, H. (INTERATOM, Bensberg, Ger.)CONF-740401--P3 - English - 1974
Abstract: not available
Key words: knk reactor;knk-2 reactor;performance;reactor protection systems;reactor shutdown;snr reactor;specifications
R&D Category: Reactor physics
display the document: 06169206.pdf
Operating experience and design criteria of sodium valves
Markford, D. (INTERATOM, Bensberg, Ger.)CONF-740964-- - English - 1974
Abstract: The information presented refers to sodium valve development for KNK and SNR-300 as well as for sodium test facilities on the INTERATOM site at Bensberg. Well in advance of KNK-I a number of sodium test facilities have been operated containing small and medium size valves of different design and manufacturer. The more stringent requirements for long range safe and reliable operation in KNK-I put forth a development program for the main primary and secondary circuit sodium valves. Operational experience gave rise to modification of the stem seal arrangement mainly, so KNK-II (which is the fast core for KNK reactor) will be run with modified sodium valves. Main pipe diameters in SNR-300 are in the range of 600 mm. Valve designs with rising shafts would require excessive space in the primary circuit cavities, therefore efforts have been directed towards introduction of different type valves. Due to the requirements of after-heat-removal a valve type with control capability had to be chosen. A special design of butterfly valves was selected for the primary and secondary circuits of SNR-300. The development and tests performed with this type of valve are described. In the field of small sodium valves, tests with a 50 mm diameter freeze-seal valve are reported, and the current status of bellows-seal-valves to be inserted into SNR-300 is discussed. (U.S.)
Key words: knk reactor;knk-2 reactor;performance;reactor cooling systems;snr reactor;sodium;valves
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 06201858.pdf
Statistical hot spot analysis of reactor cores Statistische Heisstellenanalyse von Reaktorkernen
Schaefer, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--74.26 - German - 1974
Abstract: This report is an introduction into statistical hot spot analysis. After the definition of the term 'hot spot' a statistical analysis is outlined. The mathematical method is presented, especially the formula concerning the probability of no hot spots in a reactor core is evaluated. A discussion with the boundary conditions of a statistical hot spot analysis is given (technological limits, nominal situation, uncertainties). The application of the hot spot analysis to the linear power of pellets and the temperature rise in cooling channels is demonstrated with respect to the test zone of KNK II. Basic values, such as probability of no hot spots, hot spot potential, expected hot spot diagram and cumulative distribution function of hot spots, are discussed. It is shown, that the risk of hot channels can be dispersed equally over all subassemblies by an adequate choice of the nominal temperature distribution in the core
Key words: boundary conditions;hot channel factor;hot channel;hot spot factor;knk-2 reactor;mathematical models;power distribution;reactor cores;statistics;temperature distribution
R&D Category: Reactor physics
display the document: 34087420.pdf
KNK II: Supply of the Compact Sodium Cooled Reactor Plant with a fast core (Final report for the experimental tasks of the project oriented R and D program) KNK II: Ausruestung der Kompakten Natriumgekuehlten Kernreaktoranlage mit einem Schnellen Kern (Abschliessender Bericht ueber die Versuchsvorhaben des projektgebundenen F und E Programms)
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--75.89 - German - 1975
Abstract: First considerations about the feasibility of a change over of the sodium cooled reactor KNK from a plant with a thermal core to a plant with a fast core had been started already in 1967. At that time the necessity became obvious to proof new technical developments by a construction related research and development program. For KNK the following key points were seen: construction and test of fuel assemblies, construction and test of the shutdown systems, modification and test of the handling systems and check of the neutron physics with the help of SNEAK-experiments. Part of these aspects had been covered by the test program till 1973, whereas the present report covers the period from 1973 till 1975. It describes the test results of the following subjects: test of the primary and secondary shutdown system, finalization of the handling tests and finalization of the materials testing. Finally it can be stated on the basis of the experimental results, that the components, which had been tested in the frame of this test program, will fulfil their function under the boundary conditions of a reactor plant
Key words: experiment planning;fuel assemblies;knk-2 reactor;performance testing;reactor physics;reactor safety fuses;reactor shutdown;research programs;scram
R&D Category: any or undefined
display the document: 34087409.pdf
INTERATOM Program: Program DLS
GroenefeldInternationale Atomreaktorbau G.m.b.H. (INTERATOM), Bensberg/Koeln (Germany, F.R.)
ORNL-tr--4007 - English - 1976
Abstract: Input for the two-dimensional shielding code DLS is explained in detail. Rotationally symmetrical geometries with gaps or other cavities can be investigated conveniently with this code. The calculation of the upper axial shield of the KNK-II reactor with the DLS code is included by way of example
Key words: cavities;computer codes;d codes;fortran;knk-2 reactor;neutron transport;shielding;two-dimensional calculations
R&D Category: -Analytic and numeric methods
display the document: 08305027.pdf
The carbide fuel element for the reload of the KNK-II. Das Karbid-Brennelement fuer die KNK II-Nachladung
Bojarsky, E. (Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung)KFK--2416 - German - 1976
Abstract: Within the framework of the study on the irradiation behaviour of carbide fuel rods, complete carbide fuel elements are to be tested in the fast neutron flux of the KNK II. The main data and the construction of the carbide fuel elements are presented. Some data of the KNK II carbide elements with regard to thermo-hydraulics are compared with the data of an oxide element of the type Mark II. (HR)
Key words: comparative evaluations;fuel elements;knk-2 reactor;plutonium carbides;pressure drop;specifications;testing;uranium carbides
R&D Category: Reactor physics
display the document: 08335294.pdf
The SNR-Cores: KNK-II, SNR-300 up to SNR-2. Die SNR-Kerne - KNK-II, SNR-300 bis SNR-2
Hoechel, J. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))KFK--2416 - German - 1976
Abstract: The focal points in the development of fast breeder core design are outlined briefly, and the main data of the cores Na-2, SNR-300 MK-I, SNR-300 MK-Ia and SNR-300 MK-II are presented in tabular form. Steel 1.4970 is named as a new reference material for SNR fuel elements. (HR)
Key words: fuel management;knk-2 reactor;planning;reactor cores;snr reactor;snr-2 reactor;specifications;steel-din-1-4970
R&D Category: any or undefined
display the document: 08335299.pdf
Heat transfer calculations on the KNK II emergency cooling system Waermetechnische Rechnungen zum KNK II Notkuehlsystem
Vossebrecker, H.;Groenefeld, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--76.130 - German - 1976
Abstract: The Licensing Authority had demanded that in case of the change of the KNK thermal core into a fast core the decay heat removal system must be improved by a diverse and spatially separated emergency cooling system. In order to meet this requirement an existing nitrogen system of the facility is extended in such a manner that the decay heat will be removed by a nitrogen flow passing through the gap between reactor vessel and guard vessel. The heat transport from the core to the vessel is accomplished by natural convection flow rates which are generated by density differences between the hot core subassemblies, the reflector subassemblies and other passages between the upper and the lower plenum. The calculations show that the maximum temperatures in the core do not reach the sodium boiling-point. The maximum vessel temperature is 673 deg. C. In this report the function of the emergency cooling system and the methods of calculation are described, the input data and the results are stated and it is shown that the calculated temperatures are conservative
Key words: after-heat removal;boiling points;eccs;heat transfer;knk-2 reactor;natural convection;reactor cores;reactor vessels;safety analysis;sodium
R&D Category: Safety aspects
display the document: 34087422.pdf
Basic concept and design data of a nuclear sodium boiling experiments in KNK II Grundkonzept und Auslegungsdaten eines nuklearen Na-Siedeversuches in KNK
Edelmann, MKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/5 - German - 1976
Abstract: On the basis of investigations within a feasibility study, the report describes the concept of a nuclear boiling generator as well as aspects of the nuclear and thermal-hydraulic design and instrumentation of a sodium boiling experiment in KNK II. In addition to the problems resulting from the feasibility study, first results of design calculations are presented. Therewith a common basis of available data for the solution of open questions is provided to the institutions participating in this project
Key words: boiling detection;calculation methods;design;feasibility studies;knk-2 reactor;measuring instruments;sodium;thermal hydraulics
R&D Category: Safety aspects
display the document: 34087743.pdf
Status of the USSR fast reactor programme as of March 1977
Krasnojarov, N.V.;Inyutin, E.IIWGFR--18 - Russian - 1977
Abstract: Results of experimental and applied research performance of BR-10, BOR-60 and BN-350, construction of BN-600 reactor and initial design of BN-1600 reactor are reviewed
Key words: belgium;coordinated research programs;federal republic of germany;knk reactor;knk-2 reactor;lmfbr type reactors;netherlands;snr reactor
R&D Category: any or undefined
display the document: 09363511.pdf
Documentation of the SILOE experiments results (Experiment S2) Dokumentation der SILOE Ergebnisse (Versuch S2)
Glauner, W.;Plitz, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--1210 - German - 1977
Abstract: The performance during operation of a defective sodium cooled oxide fuel rod is to be determined. For this purpose, oxide fuel rods are provided with an artificial defect in a series of tests and operated for about two months each in a sodium loop of the SILOE reactor in Grenoble. The data and mode of LMFBR operating conditions, implying partial load and full load as well as the typically slow power cyclings. That means, that LOF and TOP behavior are not investigated. Three objectives were pursued in these tests: 1. Investigation into the behaviour of the defective fuel rod power, especially questions related to defect growth. 2. Development and verification of measuring methods allowing to detect defects. 3. Determination of fuel and fission gas release from the rod and their distribution and deposition in sodium systems. The first test (S2) was performed in 1976 with a fresh fuel rod. The results obtained on the three topics indicated above are reported
Key words: coolant loops;failed element detection;fission product release;fuel element failure;international cooperation;knk-2 reactor;reactor safety experiments;siloe reactor
R&D Category: -Failure detection
display the document: 34086307.pdf
Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report Kompakte natriumgekuehlte Kernreaktoranlage mit schnellem Kern (KNK II- Karlsruhe), Sicherheitsbericht
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--78.7 - German - 1977
Abstract: After the operation of the KNK plant with a thermal core (KNK I), the installation of a fast core (KNK II) had been realized. The planning of the core and the necessary reconstruction work was done by INTERATOM. Owner and customer was the Nuclear Research Center Karlsruhe (KfK), while the operating company was the Kernkraftwerk-Betriebsgesellschaft mbH (KBG) Karlsruhe. The main goals of the KNK II project and its special experimental test program were to gather experience for the construction, the licensing and operation of future larger plants, to develop and to test fuel and absorber assemblies and to further develop the sodium technology and the associated components. The present safety report consists of three parts. Part 1 contains the description of the nuclear plant. Hereby, the reactor and its components, the handling facilities, the instrumentation with the plant protection, the design of the plant including the reactor core and the nominal operation processes are described. Part 2 contains the safety related investigation and measures. This concerns the reactivity accidents, local cooling perturbations, radiological consequences with the surveillance measures and the justification of the choice of structural materials. Part three finally is the appendix with the figures, showing the different buildings, the reactor and its components, the heat transfer systems and the different auxiliary facilities
Key words: design;fuel assemblies;heat transfer;knk-2 reactor;radiation protection;reactivity coefficients;reactor accidents;reactor cooling systems;reactor cores;reactor licensing;reactor safety;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087410.pdf
KNK II Second Core - Feasibility Study IIa KNK II Nachladung - Durchfuehrbarkeitsstudie IIa
INTERATOM GmbH, Bergisch Gladbach (Germany)INIS-DE-IA--082 - German - 1977
Abstract: The present report collects different technical notes which had been provided by INTERATOM in preparation of the licensing procedure for the second core of KNK II. Various aspects are treated, such as the core design with burnup- and power distribution, reactivity coefficients and thermal-hydraulic design, fuel availability and fabrication aspects and the design of the test and driver fuel assemblies under the aspect of their dismountabilty for post irradiation examinations
Key words: burnup;design;feasibility studies;fuel assemblies;knk-2 reactor;power distribution;reactivity coefficients;reactor cores;reactor licensing;thermal hydraulics
R&D Category: any or undefined
display the document: 34087475.pdf
Safety aspects about the installation of a nuclear boiling generator in KNK II Sicherheitstechnische Gesichtspunkte beim Einsatz eines nuklearen Siedegenerators in KNK II
Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.3/11 - German - 1977
Abstract: In this report the safety problems are described which are related to the installation of a nuclear boiling generator in KNK II. Key problems are the stress of the cladding and the safety instrumentation. Stress analysis and out-of-pile experiments so far indicate that the cladding material to be used should withstand the stresses during local boiling. The stress and strain as well as the creep and fatigue behavior due to temperature oscillations should however still be analyzed more accurately on the basis of improved material coefficients. This might not be necessary, if it can be proved, that the out-of-pile experiments give complete information about the behavior of the cladding in the nuclear generator. The instrumentation being proposed is suitable for controlling the boiling process, under the condition that the results from out-of-pile experiments can reliably be used for temperature calculations in the nuclear boiling generator. This has still to be checked. The influences of the boiling generator on possible reactor malfunctions, to be kept under control by the automatic reactor shutdown system, and on reactivity coefficients are compatible with the requirements of the reactor safety. The same holds for the special design of the boiling generator in order to limit the damage in the very unlikely event of a failure
Key words: boiling detection;creep;engineered safety systems;in core instruments;knk-2 reactor;reactivity coefficients;safety analysis;stress analysis;thermal fatigue
R&D Category: Safety aspects
display the document: 34087741.pdf
Transfer functions between the central fuel temperature, the cladding temperature and the power of fuel assemblies Uebertragungsfunktionen zwischen der zentralen Brennstofftemperatur und der Huellrohrtemperatur sowie der Leistung von Brennelementen
Ferranti, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.9/3 - German - 1977
Abstract: For the analysis of experiments, in which the heat transfer between fuel and cladding shall be deduced from the variations of the central fuel temperature, the surrounding cladding temperature and the power, the transfer functions between these parameters are required. They have been calculated in the frame of a formerly applied model. The provision of a special version of an existing computer program allowed the numerical calculation. Input data description and test sample are given
Key words: boiling detection;calculation methods;fuel elements;heat transfer;in core instruments;knk-2 reactor;temperature monitoring;transfer functions
R&D Category: -Analytic and numeric methods
display the document: 34087742.pdf
Feasibility study of a sodium boiling experiment at KNK II at nuclear power Studie zur Durchfuehrbarkeit eines Na-Siedeversuchs in der KNK II mit nuklearer Leistung
Edelmann, M.;Artz, D.;Bestenreiner, G.;Dorr, B.;Erhardt, J.;Hoppe, P.;Huber, F.;Kempe, H.;Mitzel, F.;Reimann, G.;Ricken, E.;Schaefer, L.;Schleisiek, K.;Schwarz, M.;Seitz, H.;Steinbock, K.;Vaeth, W.;Venker, H.;Zihla, WKernforschungszentrum Karlsruhe GmbH (Germany), INTERATOM;Bergisch-Gladbach (Germany)
KFK-INR--01.24.3 - German - 1977
Abstract: For testing of all potential methods to detect sodium boiling in LMFBR subassemblies, a sodium boiling experiment at KNK II is under consideration. Local boiling of sodium is to be produced behind an artificial blockage in a modified fuel element of the fast test zone of KNK II to provide approximate prototype reactor environment and operating conditions. This paper consists of a summary report on the proposed project and the results of the feasibility study and of 13 single contributions dealing with key items of the experiment. As a conclusion, the proposed experiment appears feasible and is not unlikely to be licensed by the authorities
Key words: boiling detection;experiment planning;feasibility studies;flow blockage;fuel elements;knk-2 reactor;sodium
R&D Category: Safety aspects
display the document: 34087740.pdf
Instrumentation, threshold and signal processing for the nuclear boiling generator of KNK II Instrumentierung, Grenzwerte und Signalverarbeitung fuer den nuklearen Siedegenerator an KNK II
Erhardt, J.;Hoppe, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/7 - German - 1977
Abstract: It is investigated in this report, which measuring data recorder are suitable for the control of the respective operational state and for the observation of the boiling process in the planned nuclear boiling generator of KNK II. The expected behaviour of the different measuring parameters during normal and test operation is estimated. With consideration of the irradiation and temperature loadings at the place of operation, the requirements for the data recorders are formulated and compared with the specifications of available devices. Hereby, it became obvious that a redundant and diverse safety instrumentation with flow-meters, thermocouples and neutron detectors is feasible. A threshold management for the safety relevant measuring data is proposed and a constructional arrangement of all data recorders in the instrumented plug of KNK II is given
Key words: boiling detection;data processing;feasibility studies;flowmeters;knk-2 reactor;neutron detectors;reactor monitoring systems;reactor safety;signal conditioning;thermocouples
R&D Category: Safety aspects
display the document: 34087744.pdf
Thermal-hydraulic and hydrodynamic investigations for the nuclear boiling generator in KNK II Thermohydraulische und hydrodynamische Untersuchungen fuer den nuklearen Siedegenerator KNK II
Dorr, B.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-IRE--5/01.24.3/75/77 - German - 1977
Abstract: In order to test boiling detection methods for sodium cooled fast reactors, the installation of a nuclear heated boiling generator is planned in KNK II. In this report thermal-hydraulic investigations are reported, which have been performed in the IRE for the design of this blocked fuel assembly. The following problems are treated: 1. Size of the blockage and temperature distribution within this area. 2. Conditions, under which local boiling has to be expected, 3. Hydrodynamic processes during local boiling (bubble volume, life duration of bubbles, coolant flow variations)
Key words: boiling detection;bubble growth;flow blockage;in core instruments;knk-2 reactor;reactor cooling systems;temperature distribution;thermal hydraulics;transfer functions
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 34087746.pdf
Detection of local sodium boiling in the nuclear boiling generator in KNK II and in the cores of SNR 300 and SNR 2 Nachweis von lokalem Na-Sieden im nuklearen Siedegenerator an der KNK II sowie im Core des SNR 300 und SNR 2
Erhardt, J.;Hoppe, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/9 - German - 1977
Abstract: As a basis of a global detection system, the detection of local boiling in sodium cooled reactors via surveillance of the neutron flux background noise is of special importance. With the help of parameter studies it is investigated in the present report, which parts of the core of SNR 300 and SNR 2 could be monitored with such a detection system. As a comparison the detection sensibility of the planned boiling generator in KNK II is determined
Key words: boiling detection;knk-2 reactor;neutron flux;reactor monitoring systems;reactor noise;reactor safety;snr reactor;snr-2 reactor
R&D Category: Safety aspects
display the document: 34087745.pdf
Assessment of the design of oxidic fuels and acceptance criteria for fuel elements (KNK 2, KWO). Beurteilung der Auslegungen von oxidischen Brennstoffen und Abnahmekriterien fuer Brennelemente (KNK 2, KWO)
Beisswenger, H.;Brodt, F. (Technischer Ueberwachungs-Verein Baden e.V., Karlsruhe (Germany, F.R.))AED-Conf--78-114 - German - 1978
Abstract: not available
Key words: fuel pellets;inspection;knk-2 reactor;mixtures;obrigheim reactor;performance;plutonium dioxide;quality control;reactor licensing;uranium dioxide
R&D Category: Reactor physics
display the document: 09402072.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands
Daeunert, U. (Bundesministerium fuer Forschung und Technologie, Bonn (Germany));Kessler, G. (Kernforschungszentrum Karlsruhe, Karlsruhe (Germany))IWGFR--24-2 - English - 1978
Abstract: Problems of public acceptance of nuclear power have affected the development of fast breeder reactors in the Federal Republic of Germany. Besides cooperation with UK, USA and Japan, the most outstanding event in the field of international fast breeder cooperation was a set of the agreements between Germany and France. These agreements opened the possibility of joint fast breeder development by Germany together with Belgium and the Netherlands. Most activities on the site of Compact Sodium Cooled Nuclear Reactor KNK-II were concerned with commissioning of the plant and final construction work. Criticality was achieved in Oct. 1977 and low-power tests performed. This paper includes a description of the status of construction of SNR-300 reactor and the results of research and development programmes performed. These were concerned with fuel elements development and results of irradiation experiments. Development of cladding materials and core element structural materials. Interaction between fuel and cladding. Sodium tests. Development and verification of computer codes. Experiments in fast critical assemblies. Fast rector safety. Core disruptive accidents. Development of instrumentation. Thermodynamics od fuel assemblies. Fluid dynamics
Key words: computer codes;construction;criticality;federal republic of germany;fluid mechanics;fuel elements;fuel-cladding interactions;international cooperation;knk-2 reactor;performance testing;reactor commissioning;reactor core disruption;reactor materials;reactor safety;snr reactor;verification
R&D Category: any or undefined
display the document: 32008089.pdf
On-line gamma spectroscopy system for observation of the cover gas of KNK II, description and instruction Messplatz on-line Gammaspektroskopie zur Schutzgasueberwachung an der KNK II, Beschreibung und Betriebsanleitung
Hoffmann, G.;Letz, K.DKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P02A - German - 1978
Abstract: To get more information about the further evolution of defected fuel pins in the sodium cooled fast reactor KNK II, an on-line measuring system to observe the cover gas activity was developed. A computerized gamma-spectroscope evaluates on-line some significant photo-peaks. The paper describes the hardware and software and gives an instruction manual for this system
Key words: activity levels;cover gas;failed element detection;failed element monitors;gamma spectroscopy;knk-2 reactor;on-line systems;performance testing;reactor safety
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086277.pdf
Out-of-pile experiments with an electrical boiler for Acoustic Boiling Detection Out-of-pile Experimente mit einem elektrischen Siedegenerator zur akustischen Siededetektion
Aberle, J.;Bartholomay, R.;Reimann, G.;Rohrbacher, H.A.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P01A - German - 1978
Abstract: This report contains the experimental results of boiling tests obtained during the first testing phase in spring 1977 with an electrically heated 18-rod boiling generator installed in the sodium tank facility (NABEA) of IRE. The layout and performance of the boiling facility together with its instrumentation and criteria of selection of acoustic sensors for the detection of sodium boiling are described and discussed. The report provides information about the thermodynamics, blockage design and thermal conduction within the range of installation of the electric connecting head. The evaluation of the acoustic signals shows that boiling is indicated promptly and with a sufficiently high signal-to-noise ratio both by solid-born sensors and by high temperature microphones placed in the sodium
Key words: acoustic measurements;boiling detection;flow blockage;knk-2 reactor;reactor accidents;sodium;test facilities;thermal conduction;thermodynamics
R&D Category: any or undefined
display the document: 34086288.pdf
Influence of fuel pin bowing on the temperature distribution in fuel pin cladding tubes in case of sodium cooling. Experimental results Einfluss der Stabverbiegung auf die Temperaturverteilung in Brennstabhuellrohren bei Natriumkuehlung - Experimentelle Ergebnisse -
Moeller, R.;Tschoeke, H.;Kolodziej, MKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.23P01D - German - 1978
Abstract: The influence of rod bowing on the local temperature distribution was measured with turbulent sodium flow in the cladding tubes of a 19-rod bundle mock-up of the SNR 300 Mark Ia fuel element. Such measurements have been carried out for the first time. The results presented in this report are part 1 of the experimental evaluation not yet completed. The major results are: 1. When a rod on the first ring gets deformed towards a neighbour on the second ring with a gap reduction from the nominal value of 100 % down to 20 %, the maximum azimuthal temperature difference of the outer rod increases by about 60 %. 2. The maximum azimuthal temperature difference of a rod on the first ring increases by a factor of 2, if it is approached by a neighbour on the same ring. 3. The reduction in cross section of a subchannel by rod bowing results only locally in distinct temperature rises, i.e. in the adjacent cladding tubes. Rods of the next but one row are no more subject to noticeable changes in temperature
Key words: bowing;deformation;design;fuel assemblies;knk-2 reactor;sodium;temperature distribution;testing;thermal hydraulics;turbulent flow
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086298.pdf
Concepts of annular fuel elements for installation of irradiation inserts in KNK II and layout of a carbide test bundle Konzepte ringfoermiger Brennelemente zur Aufnahme von Bestrahlungseinsaetzen in KNK II und Entwurf eines Karbidkleinbuendels
Haefner, H.E.;Philipp, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.02P03C - German - 1978
Abstract: A variety of basic proposals for the irradiation of test fuel elements in the test zone of KNK II are being discussed recently. As a further concretization annular fuel elements with two or three rows of oxide fuel pins for the installation of different irradiation devices are considered. In this report the layout of a carbide test bundle in a carrier element with two pin rows is proposed
Key words: annular fuel elements;fuel assemblies;fuel pins;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;specifications
R&D Category: Reactor physics
display the document: 34086299.pdf
The behavior of the fuel pins of the fuel element NY 205 of KNK II Zum Verhalten der Staebe des Brennelementes NY 205 aus der KNK II
Goetzmann, OKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.03P02A - German - 1978
Abstract: The fuel element NY 205 has been irradiated in the first and in the second core of KNK II up to a maximum local burnup of 18.6 % with a total residence time of 832 equivalent full-power days and a maximum local steel damage of 66 dpa-NRT. Because of a fuel pin failure it was unloaded on May 28, 1987 and carried to the Hot Cells of the Karlsruhe Research Center. The results of the post-irradiation examinations and the conclusions to be drawn are described in this report. The pin claddings, made of the steels 1.4970 and 1.4980, experienced expansion due to swelling with maxima around or just below core mid-plane. The axial redistribution of volatile fission products lead to an accumulation in the upper third of the fissile column. In this area the inner clad corrosion was most intensive with a depth of up to 130
Key words: burnup;cladding;corrosion;fission products;fuel element failure;fuel pins;knk-2 reactor;performance testing;post-irradiation examination;spacers;swelling
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086301.pdf
Local coolant flow perturbations in KNK II - coolant inlet blockages of assemblies of the test and driver zone Lokale Kuehlflusstoerungen in KNK II - Kuehlmitteleinlaufblockaden von Elementen der Test- und Treiber-zone
Duesing;Friedel;GerlingINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.670.4 - German - 1978
Abstract: The present report documents the investigations of local coolant blockages, which were requested for KNK II from the licensing authorities. Sudden blockages at the coolant inlet of fuel assemblies are assumed of such a degree that sodium boiling occurs. Four basic cases have been defined, three for the central fuel assembly with different nominal power levels and different residual coolant flow and one for a moderated driver assembly with 100% power and 10% residual flow. For these cases the course of the accident has to be followed for each scram excitation into the post-scram phase. It had to be proved, that these perturbations are controlled by the inherent properties and the preventive safety measures of the KNK II and that their extension is prevented. It is shown that this proof target is reached. From the calculational results for the basic cases statements are deduced for the accident detection and the accident course for the whole spectrum of integral coolant flow reduction accidents. The aimed high efficiency of the preventive measures, especially in the test zone, is hereby confirmed
Key words: boiling;flow blockage;fluid flow;knk-2 reactor;loss of flow;reactor accidents;risk assessment;safety analysis;scram;sodium
R&D Category: Safety aspects
display the document: 34087395.pdf
Nuclear startup of the Compact Sodium Cooled Nuclear Power Plant KNK II, Zero Power Tests Nukleare Inbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II, Nulleistungspruefungen
Feltes, W.;Richard, H.;Schmidt-Hoenow, M.;Stroemich, A.;Wilhelm, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--78.48 - German - 1978
Abstract: The report describes the nuclear startup of the KNK II reactor at zero power, comprising core loading, control rod calibration and determination of reactivity coefficients. Additionally, the accompanying calculations and a valuation of the results are documented. The comparison of important design parameters, such as critical fuel assembly number, control rod worths and sodium-void reactivity, with the experimental results shows agreement within the error margins
Key words: comparative evaluations;control elements;control rod worths;experimental data;knk-2 reactor;reactivity coefficients;reactor fueling;reactor start-up;sodium;theoretical data;void coefficient
R&D Category: Reactor physics
display the document: 34087423.pdf
KNK II, Compact Sodium-Cooled Reactor in the Nuclear Research Center Karlsruhe
INTERATOM GmbH, Bergisch-Gladbach (Germany)INIS-DE-IA--013 - English - 1978
Abstract: The report gives an overview of the project of the sodium-cooled fast reactor KNK II in the nuclear research center KfK in Karlsruhe. This test reactor was the preparatory stage of the prototype plant SNR 300 and had several goals: to train operating personal, to practice the licensing procedures in Germany, to get experience with the sodium technology and to serve as a test bed for fast breeder core components. The report contains contributions of KfK as the owner and project managing organization, of INTERATOM as the design and construction company and of the KBG as the plant operating organization. Experience with and results of relevant aspects of the project are tackled: project management, reactor core and component design, safety questions and licensing, plant design and test programs
Key words: construction;knk-2 reactor;program management;reactor cores;reactor licensing;reactor operation;safety analysis;training
R&D Category: any or undefined
display the document: 34087474.pdf
Nuclear startup of the compact sodium-cooled nuclear power plant KNK II, zero power tests Nukleare Inbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II, Nulleistungspruefungen
Richard, H.;Schmidt-Hoenow, M.;Feltes, W.;Stroemich, A.;Wilhelm, HKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
INIS-DE-KBG--013 - German - 1978
Abstract: This report describes the nuclear start-up phase of KNK II at zero power. The first criticality was achieved on October 10th, 1977, and the experiments were finished on November 5th, 1977. The core loading, the absorber calibration and the determination of the temperature coefficients are described in the report, and the results are compared with precalculations. The mission of the start-up program is the experimental prove of safety relevant core parameters such as surplus reactivity and control rod worths on one side, and on the other side the experiments allow a test of the experimental and calculational methods in view of the design and the licensing of future KNK II cores. The comparison of measured and calculated values shows agreement within the error limits
Key words: calculation methods;comparative evaluations;control rod worths;criticality;design;experimental data;knk-2 reactor;reactivity coefficients;reactor cores;reactor safety;reactor start-up;temperature coefficient
R&D Category: Reactor physics
display the document: 34087483.pdf
The KNK II test program Das KNK II Versuchsprogramm
Kathol, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.04P00A - German - 1978
Abstract: The sodium cooled fast reactor KNK II in the Research Center of Karlsruhe with a thermal power of 58 MW and an electric power of 20 MW has the mission to collect experience for the construction and operation of the German fast breeder prototype SNR 300. First criticality of the reactor was reached on October 10, 1977 and the license for full-power operation was given on August 3, 1978. The test program for KNK II comprises the following areas: irradiation experiments with the corresponding post-irradiation examination, fuel cycle, instrumentation and detection techniques, operation related experiments and reactor chemistry. These areas with their specific experimental programs are described in the report, after an illustration of the properties of KNK II as an irradiation reactor
Key words: fuel cycle;knk-2 reactor;materials testing;post-irradiation examination;reactor instrumentation;research programs
R&D Category: any or undefined
display the document: 34087763.pdf
Axial fission rate distribution in SNEAK 11A Axiale Spaltratenverteilung in SNEAK 11A
Moellendorff, U. von;Henneges, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02E - German - 1978
Abstract: In SNEAK 11A -the simulation of a possible reload core of KNK II- axial fission rate distributions of U235, U238 and Pu239 were measured with two independent methods. They are compared with results of r-z-diffusion calculations. For the unexpectedly strong axial asymmetry of the distributions of U235 and Pu239 a qualitative explanation is given
Key words: fission;knk-2 reactor;neutron diffusion equation;nuclear reaction kinetics;plutonium 239;reactor cores;reactor fueling;reactor kinetics;sneak reactor;spatial distribution;two-dimensional calculations;uranium 235;uranium 238;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087773.pdf
Investigations concerning gas entrainment at KNK II. Untersuchungen zum Gaseintrag an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--2867 - German - 1979
Abstract: During commissioning of KNK II operational difficulties were encountered due to gas entrainment in the coolant. This gas entrainment caused negative reactivity fluctuations which tripped the reactor repeatedly. Since first investigations indicated one main cause of the gas entrainment and the existence of an accumulation process a technical modification (installation of a throttle valve) for remedy was performed. By means of this valve the gas entrainment could be considerably reduced but not completely eliminated. The gas storages can be localized with high probability to a region in the primary coolant circuit between a special throttle device and the lower part of the fuel elements. A permanent gas entrainment could be detected even at operational plant conditions (40% reactor power) at which no scrams due to entrained gas bubbles have been encountered. The volume fraction referred to the coolant volume in the core was estimated to be at least 10-4. The observation of apparently positive reactivity overshoots is due to the application of an erroneous reactivity to power transfer function for the reactivity calculation. From the use of the measured reactivity to power transfer function it can be concluded that only negative reactivity fluctuations are induced by gas bubbles passing the core. (orig./HP)
Key words: entrainment;fluctuations;gases;knk-2 reactor;reactivity;reactor commissioning;reactor operation;reactor start-up;valves
R&D Category: Commissioning and start-up testing, rise to power, transient testing
display the document: 11514378.pdf
Status of the DEBENE fast breeder reactor development, March 1979
Daeunert, U.;Kessler, GIWGFR--30-2 - English - 1979
Abstract: Status report of the Fast-breeder reactor development in Germany covers the following: description of the political situation in Federal republic of germany during 1978. International cooperation in the field of fast reactor technology development. Operation description of the KNK-II fast core experimental power plant. Status of construction of the SNR-300. Results of the research and development programs concerned with fuel element, cladding, absorber rods and core structural materials development. Sodium effects. Neutron irradiation effects on SS properties. Reactor physics related to experiments in fast critical assemblies. Fast reactor safety issues. Core disruption accidents. Sodium boiling experiments, measuring methods developed. Component tests
Key words: cladding;fuel elements;knk-2 reactor;measuring methods;performance testing;radiation effects;reactor components;reactor core disruption;reactor cores;reactor safety;snr reactor;sodium;stainless steels;technology assessment
R&D Category: any or undefined
display the document: 33014309.pdf
Design report for core assemblies of KNK II: Driver zone assemblies with moderator Auslegungsbericht fuer Kernelemente KNK II: Treiberzonenelemente mit Moderator
Huesken, J.;Fenneker, K.;Singer, J.;Zihla, W.;Coors, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.01910.8 - German - 1979
Abstract: The report describes the driver zone fuel assemblies with moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;safety standards;specifications;zirconium hydrides
R&D Category: Reactor physics
display the document: 34085694.pdf
Design report for core assemblies KNK II/2: Secondary shutdown assemblies Auslegungsbericht fuer Kernelemente KNK II/2: Zweitabschaltelemente
Koenigsdorf, E.;Huesken, J.;Schmitz, K.J.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03541.1 - German - 1979
Abstract: The report describes the secondary shutdown assemblies of the second core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;calculation methods;design;knk-2 reactor;neutron absorbers;reactor shutdown;scram rods
R&D Category: Reactor physics
display the document: 34085700.pdf
Design report for core assemblies KNK II/2: Standard control assemblies and control assemblies with test pins Auslegungsbericht fuer Kernelemente KNK II/2: Standard-Regeltrimmelemente und Regeltrimmelemente mit Versuchsstaeben
Ricken, E.;Schmitz, K.J.;West, G.;Sperber, F.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04177.9 - German - 1979
Abstract: The report describes the control assemblies of the second core of KNK II and their operational behavior during the foreseen residence time of 455 equivalent full-power days. There are three standard assemblies with closed pins with B4C pellets, one assembly with 49 pins filled with B4C pellets and three pins each filled with Eu2O3 and EuB6 pellets and one assembly, in which degassed pins with diving bell or porous plug, respectively, will be tested. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;burnable poisons;burnup extension;calculation methods;control elements;europium borides;europium oxides;fuel cycle;knk-2 reactor;neutron absorbers;reactor cores;reactor safety;scram rods
R&D Category: Reactor physics
display the document: 34085703.pdf
Detection of the first fuel pin failure in KNK II Detektion des ersten defekten Brennstabs in der KNK II
Hoffmann, G.;Jacobi, S.;Jonatzke, O.;Letz, K.D.;Schmitz, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P22A - German - 1979
Abstract: This report describes the detection of the first failed fuel pin in KNK II on April 1st, 1979. The DND signals of the background of both DND monitors installed near the main sodium pipes are compared with the signals after the beginning of the failure. The free fuel surface was estimated at about 1 mm''2 from the signal amplitudes. Immediately after the beginning of the failure the online-gamma-spectrometer started a special measurement, this spectrum is also compared with the background spectrum
Key words: defects;delayed neutron analysis;failed element detection;fuel element failure;fuel pins;gamma spectroscopy;knk-2 reactor;neutron detection;on-line control systems;reactor safety
R&D Category: -Failure detection
display the document: 34086280.pdf
Measurement and calculation of the reactivity-to-power transfer function of KNK II for the examination of the reactivity coefficients of the first core Messung und Berechnung der Reaktivitaets-Leistungs-Uebertragungsfunktion von KNK II zur Ueberpruefung von Reaktivitaetskoeffizienten der Erstbeladung
Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P09A - German - 1979
Abstract: Measurements of the reactivity-to-power transfer function were performed in the first core of KNK II with the goal to examine the reactivity coefficients. The experimental and calculational results were compared with inclusion of the static power coefficient. The measured transfer functions showed much stronger burnup dependences than the calculated ones. One anomaly of transitory character occurring immediately after reaching full-power could not be explained till now. Different indications seem to point on a nonuniform burnup behavior. Due to the partly good agreement between the measured and calculated transfer function and the nevertheless existing discrepancy with the static power coefficient it can be concluded, that the discrepancy may be caused by a not yet considered negative reactivity effect with a relatively large time constant. At the end of the operational phase further differences between calculated and measured transfer function were observed. They could have been caused by a reduction of the bowing coefficient due to swelling. Since the burnup has obviously a much stronger influence on the experimental results, this type of measurements should be repeated in the next core with shorter time intervals
Key words: bowing;comparative evaluations;experimental data;knk-2 reactor;power coefficient;reactivity coefficients;theoretical data;transfer functions
R&D Category: Reactor physics
display the document: 34086290.pdf
Vibration measurements at KNK II Schwingungsmessungen an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P05D - German - 1979
Abstract: For the development of surveillance techniques, vibration measurements have been performed at the sodium cooled fast reactor KNK II. For this purpose the signals of neutron detectors, sodium pressure gauges, displacement transducers and strain gauges, some of them being installed within the core, have been analyzed by means of noise analysis methods. The power spectral densities of the neutron flux and the sodium pressure show distinct correlated peaks indicating vibrations of core internals
Key words: fuel assemblies;knk-2 reactor;mechanical vibrations;neutron detectors;performance testing;reactor cores;reactor noise;sodium;strains;transducers
R&D Category: Safety aspects
display the document: 34086289.pdf
Investigations of gas entrainment in KNK II Untersuchungen zum Gaseintrag an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P25A - German - 1979
Abstract: During commissioning of KNK II operational difficulties were encountered due to gas entrainment in the coolant. This gas entrainment caused negative reactivity fluctuations which tripped the reactor repeatedly. Since first investigations indicated one main cause of the gas entrainment and the existence of an accumulation process, a technical modification (installation of a throttle valve) for remedy was performed. This report describes the investigations made after the plant modification. The main objective was to test the effectiveness of the modifications and to look into the following still open problems: Localization of the gas storage, detection and estimation of a permanent gas entrainment and the analysis of positive power overshoots being observed in connection with the gas bubbles
Key words: bubbles;entrainment;gases;knk-2 reactor;performance testing;reactivity insertions;reactor accidents
R&D Category: Safety aspects
display the document: 34086291.pdf
Detection of local cooling disturbances in the core of SNR 300 by Delayed Neutron Detection DND and by fuel element outlet temperature surveillance Detektion lokaler Kuehlungsstoerungen im Kern des SNR 300 durch DND-System und Ueberwachung der Brennelementaustrittstemperatur
Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.19P21A - German - 1979
Abstract: In this report the possibilities of the detection of local cooling disturbances in the core of SNR 300 by Delayed Neutron Detection DND and fuel element outlet temperature monitoring are analyzed. At the given DND scram level of 150 cm2 effective free fuel surface in the most unfavourable zone of the core, the fuel mass within a local blockage will not exceed 120 g. In the MOL 7C experiments it has been demonstrated that blockages of this size do not have the potential for a fast failure propagation to the fuel element as a whole. The local destruction of fuel pins after the occurrence of dry-out within a local blockage is reliably detected by the DND system with a time delay corresponding to the sodium transport time to the DND monitor. Even at a fast reduction of the sodium flow leading to bulk boiling and melting in the fuel element, DND signals can be expected which are sufficient to initiate a reactor scram. Many events of the propagation process cause a temperature increase at the fuel element outlet, too. In most cases however, the DND is superior to the temperature surveillance with respect to the sensitivity, except for blockages at the fuel element inlet. In this case a distinct temperature signal can be expected prior to the occurrence of pin failures as a consequence of the temperature increase
Key words: delayed neutron analysis;dryout;flow blockage;fuel element failure;knk-2 reactor;neutron detection;reactor accidents;snr reactor;sodium;temperature monitoring
R&D Category: Safety aspects
display the document: 34086297.pdf
The irradiation of carbide fuel pins in the frame of the Fast Breeder Project Die Bestrahlung von Karbid-Brennstaeben im Rahmen des PSB
Steiner, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.03P23C - German - 1979
Abstract: The report gives an overview of the present status and the most important results of the carbide-program of the Fast Breeder Project PSB. Only integral fuel pin irradiation experiments are considered. The PSB-program is characterized by a plurality of parameter variations, partly within large ranges. The most important variations concern the concept of the bonding, the smear- and pellet-density, the fabricated gap width between fuel and cladding as well as the irradiation conditions for the pin power, cladding temperature and burnup. In view of the small number of test samples the inclusion of the international irradiation experience is a great advantage. The results with the gas-bonded fuel pins indicate, that the achievable burnup increases when the smear density is decreased from 85 % to 80 %. Burnups of 7 % and more together with linear powers of 800 - 1100 W/cm can only be reached with smear densities of 80 % or less. For sodium-bonded pins, the defect-rate is smaller than for gas-bonded pins. Out of the four observed defects two were caused by failures of the capsule and the others by excessive cladding carburization. Besides questions of concept valuation, the present report also discusses some important aspects of the irradiation behavior of carbide samples, such as thermal behavior and mechanical interaction between fuel and cladding and carburization
Key words: burnup;carburization;cladding;fuel pellets;irradiation;knk-2 reactor;mixed carbide fuels;physical radiation effects
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086300.pdf
Investigation of different reactor protection systems Untersuchung verschiedener Reaktorschutzsysteme
Eggenberger, O.;Gmeiner, L.;Nehmer, J.;Racke, W.;Voges, UKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--01.02.19P23A - German - 1979
Abstract: It is the goal of this report to evaluate and to compare the computerized reactor protection systems of different existing plants and to develop a methodology for application in fast reactors and to be tested in KNK II. Within the 14 plants under investigation four are fast reactors and the others are thermal reactors
Key words: computerized control systems;fast reactors;knk-2 reactor;performance testing;reactor protection systems;thermal reactors
R&D Category: Safety aspects
display the document: 34086370.pdf
Test of In-core Flux Detectors in KNK II
Hoppe, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-PSB--010 - English - 1979
Abstract: The development of in-core detectors for Liquid Metal Fast Breeder Reactors (LMFBRs) is still in an early stage, and little operation experience is available. Therefore self-powered neutron and gamma detectors and neutron sensitive ionization chambers -especially developed for LMFBRs- have been tested in the Fast Sodium Cooled Test Reactor KNK II. Seven flux detectors have been installed in the core of KNK II by means of a special test rig. Five of them failed already within the first week during operation in the reactor. Due to measurements of electrical resistances and capacities, sodium penetrating into the detectors or cables probably seems to be the cause. As tests prior to the installation in the core proved the tightness of all detectors, it is suspected that small cracks have developed in the detector casings or in the outer cable sheaths during their exposure to the hot coolant. Two ionization chambers did not show these faults. However, one of them failed because the saturation current plateau disappeared and the other one's sensitivity decreased by a factor of five during the test period. It is suspected that in both cases changes of the filling gas might be involved
Key words: in core instruments;ionization chambers;knk-2 reactor;neutron detectors;neutron monitors;performance testing;self-powered gamma detectors
R&D Category: any or undefined
display the document: 34087494.pdf
KNK II - JOYO Information Exchange, Proceedings of the 3rd Expert-Meeting
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-KFK--014 - English - 1979
Abstract: The third KNK II - JOYO information exchange meeting from March 14 to 16, 1979 was held at a moment when both reactors had reached full power operation. The conference took place at the Kernforschungszentrum Karlsruhe, at INTERATOM in Bergisch Gladbach and at the site of the SNR 300 at Kalkar. The main topics of the reports and discussions were the core characteristics of both facilities during power operation, the operational experience with several plant components and the problem due to gas bubbles at KNK II. At this meeting a representative of the CEA, France, participated for the first time
Key words: boiling detection;bubbles;entrainment;international cooperation;joyo reactor;knk-2 reactor;reactor components;reactor cores;reactor operation
R&D Category: any or undefined
display the document: 34087491.pdf
Subcritical experiments in SNEAK 11B1 Unterkritische Experimente in SNEAK 11B1
Henneges, G.;Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02F - German - 1979
Abstract: SNEAK 11B1 was the simulation of the first reload of KNK II with four Mark-I and three Mark-II fuel elements in the test-zone. In the critical state the simulated absorber rods were withdrawn till core upper plane. The reactivity worths of these rods in different insertion configurations were determined with two different subcritical measurement techniques. Values of up to -28 dollar were measured. The present report presents all measured values, calculated results and the correction calculations for the source multiplication measurements. The results are discussed, especially with respect to the suitable detector positions
Key words: comparative evaluations;control elements;control rod worths;experimental data;fuel elements;knk-2 reactor;neutron absorbers;reactivity insertions;sneak reactor;subcritical assemblies;theoretical data;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087774.pdf
On-line gamma spectroscopy measuring station for cover gas monitoring at KNK II
Hoffmann, G.;Letz, K.DKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--2797 - English - 1980
Abstract: An automated Ge-
Key words: automation;cover gas;failed element monitors;fuel cans;gamma spectrometers;ge semiconductor detectors;knk-2 reactor
R&D Category: -Failure detection
display the document: 11536175.pdf
Simulation of fuel element thermal hydraulics for sensitive monitoring of coolant flow
Edelmann, M. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)GRS--19 - English - 1980
Abstract: The sensitivity of outlet temperatures for cooling disturbances can be improved significantly by eleminating temperature noise and variations of the temperature rise of a subassembly due to inlet temperature and power noise or control of the reactor power level. This has been demonstrated at the KNK II. The different types of KNK fuel elements were modeled by individual combinations of two first-order low-pass filters, one for the fuel element and one for the thermocouple. Using a neutron detector signal as input for these filters provides simulated outlet temperature signals for comparison with the measured signals. Under stationary conditions of reactor operation these signals agreed within less than 1 K. For non-stationary conditions a more general model of the fuel element was applied. In this model time-dependent thermohydraulic parameters could be used. In this way a cooling disturbance consisting of gas bubbles in the sodium was simulated. A sensitivity study showed that gas bubbles of 1% of the sodium volume in the fuel region could be detected at KNK II in spite of the power drop caused simultaneously by the negative sodium void effect. (orig./HP)
Key words: disturbances;flow blockage;flow rate;knk-2 reactor;loss of flow;reactor control systems;reactor noise;temperature control
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 13665581.pdf
Annual meeting on nuclear technology 1980. Technical meeting: Operating experiences. Jahrestagung Kerntechnik 1980. Fachsitzung: Betriebserfahrungen
Deutsches Atomforum e.V., Bonn (Germany, F.R.)INIS-mf--10622 - German - 1980
Abstract: In addition to general experiences, experiences in reactor operation with relation to the Phenix reactor, KNK-2 reactor, the AVR reactor, the BWR-type KKI-reactor, the Philippsburg-1 reactor and the Obrigheim reactor are described. (DG)
Key words: availability;avr reactor;isar reactor;knk-2 reactor;obrigheim reactor;performance;phenix reactor;philippsburg-2 reactor;radiation protection;radioactive effluents;reactor operation
R&D Category: any or undefined
display the document: 18052413.pdf
Operating experiences with the KNK-2 reactor. Betriebserfahrungen mit KNK II
Brudermueller, G. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.))INIS-mf--10622 - German - 1980
Abstract: Experiences with KNK confirm that a natrium-cooled nuclear power station can be operated sensibly, that relatively few really major problems specific to natrium have been encountered in the KNK reactor and that those problems which do exist, or have existed in the past, are largely historic to KNK or are due to the layout details characteristic of KNK. The gas bubbles problem is also included in this category and should not be considered as typical for natrium reactors. (orig./DG)
Key words: bubbles;cover gas;failed element detection;knk-2 reactor;reactor maintenance;reactor operation;scram
R&D Category: any or undefined
display the document: 18052719.pdf
Pin, assembly and core design for the extended residence time of the first core of KNK II Stab-, Element-, und Kernauslegung fuer den verlaengerten Betrieb des Erstkerns der KNK II
Fenneker, K.;Menssen, R.;Ricken, E.;Spenke, H.;Sperber, F.;Wehmann, U.;West, GINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--33.02587.1 - German - 1980
Abstract: The present report describes the performance of the whole core, the assemblies and their pins of the first core of KNK II during the residence time extension by 100 equivalent full-power days (efpd) beyond the foreseen 255 efpd. The extension can be realized by making use of the reactivity reserve of the present first core and by loading of two reserve fuel assemblies. The design methods, as far as they differ from those used for the first core, and the results of the pin design, subassembly design and core design are described
Key words: burnup extension;configuration;design;fuel assemblies;fuel pins;knk-2 reactor;reactor cores
R&D Category: Reactor physics
display the document: 34085695.pdf
Development of an absorber pin with diving bell Entwicklung eines Absorberstabes mit Tauchglocke
Dreyer, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03724.4 - German - 1980
Abstract: The report describes the development of an absorber pin with diving bell (degassed absorber) at INTERATOM since 1974. In comparison with the closed absorber pin, which is presently foreseen for SNR 300, the degassed absorber pin offers the advantage of a longer residence time, since it allows the release of the Helium produced in the boron absorber material and thus avoiding a mechanically straining pressure built-up. During the period from 1974 till 1979 seven major experiments for the test of the diving bell concept had been performed at INTERATOM: five in stagnant sodium, one scram-test in sodium and one bundle test in water. All tests confirmed the operational efficiency of the absorber pin with diving bell. Major affects on the behavior of the concerned materials could not be detected. The development work for the absorber pins with diving bell will be continued with the loading of eight of these pins in KNK II/2 in 1981
Key words: boron carbides;boron;degassing;fuel elements;interstitial helium generation;knk-2 reactor;neutron absorbers;performance testing;research programs;snr reactor
R&D Category: Reactor physics
display the document: 34085701.pdf
KNK II, MTE II design report, temperature distribution KNK II, MTE II-Auslegungsbericht, Temperaturverteilung
Puetz, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--33.02637.0 - German - 1980
Abstract: The present report deals with the calculation of the temperature distribution in the Material-Test-Element (MTE II) for KNK II/2. The calculational method includes the influences of the bypasses between the assemblies and the neighbouring assemblies. In the chosen reference case (MTE II mass-flow 0.1 kg/s, bypass mass-flow 0.185 kg/s) a temperature rise of 70 K is reached. The power of the MTE II is 24.8 kW
Key words: calculation methods;design;fuel elements;knk-2 reactor;temperature distribution;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085696.pdf
Release of fission products from the KNK II fuel element failure and search for released fuel in the primary sodium Freisetzung von Spaltprodukten aus dem KNK II-Brennelementschaden und aktivierungsanalytische Suche nach ausgetragenem Brennstoff im Primaernatrium
Hanke, H.-D.;Clauss, H.;Stamm, H.-HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P24B - German - 1980
Abstract: A first fuel element cladding failure occurred in the KNK II reactor on April 1st, 1979. The activity concentrations of radio nuclides are reported from four sodium samplings: the last sampling before the fuel failure, two samplings with the failed element in the core and one sampling after removal of the failed fuel element. Only I-131, Cs-136 and Cs-137 were released from the failed fuel into the primary sodium. The release fraction of Cs-137 was 5.2 % of a fuel rod inventory. The specific activities of some radio nuclides (Zn-65, Ag-110m, Sb-124,...) in the primary coolant were determined by neutron activation analysis. In addition, efforts were made to find non-radioactive cesium and released fuel in the sodium. The applied procedure is described in detail. Neither in the recent samples nor in Na stock samples from the time before nuclear operation of the plant any cesium or fuel was detected. From detection limits it was concluded, that the Cs content in the 21 metric tons of primary sodium was smaller than 10 mg and the content of fuel smaller than 1.1 mg
Key words: after-heat removal;antimony 124;cesium 136;cesium 137;defects;delayed neutron analysis;fission product release;fuel element failure;iodine 131;knk reactor;knk-2 reactor;neutron activation analysis;neutron detection;primary coolant circuits;silver 110;sodium;testing;zinc 65
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086281.pdf
Investigations of the gas passage through the reactor core of KNK II Untersuchungen zu den Gasdurchlaeufen durch den Reaktorkern KNK II
Hoechel, J.;Schott, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--75.01284.1 - German - 1980
Abstract: During the startup phase of KNK II automatic scrams due to the signal 'reactivity too low' occurred when a power level above 60 % was reached. Comprehensive plant experiments at zero power were performed to find out the reason for the reactivity effects. It became clear that the transport of gas bubbles through the core was the reason. With the help of several further experiments it could be shown that the gas discharge pipe of the nozzle modification equipment was the major gas source. After reduction of the mass-flow through this pipe with the help of a throttle, a stationary operation of the plant was possible. This report describes the results of the experimental investigations at the plant in the frame of the experimental operation and those which were performed in parallel on different water models
Key words: entrainment;fuel elements;gases;knk-2 reactor;reactivity insertions;reactor cores;reactor operation
R&D Category: Safety aspects
display the document: 34087407.pdf
Model experiments for the problem of the gas storage and gas transport in the KNK reactor Modellversuche zum Problem der Gasspeicherung und des Gastransports im KNK-Reaktor
Voj, P.;Granner, N.;Penny, WINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--53.03970.1 - German - 1980
Abstract: During the start-up phase of KNK II an automatic scram due to the signal 'negative reactivity high' occurred at a power level of 64%. The reactivity threshold of the reactimeters was at -7.3 cent. In the frame of the examinations of the cause for the scram it was found out, that mechanical changes in the core area were not the reason. Since further scrams occurred, specific plant experiments at zero power were performed with the result, that gas transported with the sodium was identified as the origin of the reactivity perturbations. It could be shown, that the gas quantities under discussion were no safety related problem. But they reduced the availability of the plant and limited the frame of the planned operational procedures of the test reactor. This report presents the results of model experiments in water, which were performed in parallel to the plant experiments
Key words: entrainment;gases;knk-2 reactor;reactivity meters;reactivity;reactor start-up;sodium
R&D Category: Safety aspects
display the document: 34087403.pdf
Safety related investigations for the second and third operation period of KNK II Sicherheitstechnische Untersuchungen fuer die zweite und dritte Betriebsperiode der KNK II
Friedel, G.;Groenefeld, G.;Lenzen, M.;Niebel, H.;Pueschel, H.;Schade, H.-J.;Stepan, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--70.01486.9 - German - 1980
Abstract: The present report contains the safety analysis performed for the second core of KNK II in the operation period from 256 to 710 equivalent full-power days. It is separated into the following six chapters: 1. Operational and accidental performance. 2. Local cooling flow disturbations. 3. Operational and accidental behavior of the primary heat transfer circuits. 4. Investigation of the emergency cooling performance. 5. Thermo-technical investigations of the fuel assemblies during handling. 6. Activities in the plant and radiological effects in case of normal operation and accidents
Key words: dynamics;eccs;fluid flow;fuel assemblies;heat transfer;knk-2 reactor;primary coolant circuits;radiation protection;reactor cores;safety analysis;steady-state conditions;thermal analysis;transients
R&D Category: Safety aspects
display the document: 34087418.pdf
First KNK II Seminar, September 1980 Erstes KNK II Seminar, September 1980
Kathol, WKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-KFK--016 - German - 1980
Abstract: The installation of the KNK II Seminar is a new way to follow the whole project. The various problems of an operating plant with the fuel assembly supply, the actual operation and the final disposal are presented and discussed during this seminar
Key words: fuel assemblies;knk-2 reactor;radioactive waste disposal;reactor operation;reactor safety
R&D Category: any or undefined
display the document: 34087492.pdf
BMFT-CEA-US-DOE Exchange on Fast Breeder Reactors, Proceedings of the 1st Expert-Meeting at Karlsruhe March 24 and 25, 1980
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-KFK--017 - English - 1980
Abstract: The present report compiles the papers presented at the first exchange meeting on operating experience of EBR II-, Rapsodie- and KNK II at Karlsruhe in March 1980
Key words: ebr-2 reactor;international cooperation;knk-2 reactor;rapsodie reactor;reactor operation;reactor safety
R&D Category: any or undefined
display the document: 34087493.pdf
Comparison of diffusion- and transportcode-results in the course of the evaluations of the SNEAK 11B1 control rod experiments Vergleich von Diffusions- und Transportcode-Ergebnissen bei der Auswertung von Kontrollstabexperimenten im Rahmen des SNEAK 11B1-Experimentierprogramms
Henneges, G.;Kuefner, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P43B - German - 1980
Abstract: SNEAK 11B1 was the simulation of the first reload core of KNK II. Extensive subcritical control rod worth experiments were performed in this assembly. The evaluation of these experiments with diffusion codes revealed ratios between calculated and measured values in the range of 1.03 to 1.21. To clarify this large spread, transport calculations and parametric studies were performed. In this report the results of SN-calculations are described and compared with diffusion results, and discrepancies are pointed out. The determination of the neutron flux level at the detector position is not possible with SN-codes since ray-effects are preventing meaningful evaluations. The comparison of diffusion- and transport-results is also showing considerable discrepancies
Key words: calculation methods;control rod worths;discrete ordinate method;knk-2 reactor;neutron diffusion equation;neutron flux;sneak reactor;subcritical assemblies;zero power reactors
R&D Category: Reactor physics
display the document: 34087776.pdf
KNK II irradiation project of an annular element with 19-pin carbide test bundle on a ring position of the test zone KNK II Bestrahlungsvorhaben Ringelement mit 19-Stab Karbidtestbuendel auf einer Kranzposition der Testzone
Haefner, H.E.;Steiner, H.;Weinberg, D.;Norajitra, P.;Frey, H.HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P42A - German - 1980
Abstract: The carbide fuel is considered as a promising long-term alternative to the oxide fuel for fast breeder reactors. Also the KfK is working since 1968 in the frame of the fuel element development program of the Fast Breeder Project (PSB) on carbide fuels, whereby until now the main effort was spent on the carbide fabrication and the irradiation behavior of single pins. One result of these activities is the KfK carbide reference concept: low pellet density, relatively large gap and helium bonding between fuel and cladding. As completion of the past work a small carbide test bundle with 19 pins is planned to be irradiated in KNK II under sufficient representative conditions. To provide a corresponding irradiation channel, an annular oxide carrier element is being developed, which can also accommodate other test inserts in future. Characteristic design data of the carbide element are the following: pin diameter 8.5 mm, pellet diameter 7.0 mm, maximum nominal pin linear rating 800 W/cm, maximum nominal burnup 70 MWd/kgHM. Besides a short description of the combined element, the report contains the design and operational data for the test bundle and the carrier element, a first thermohydraulic design of both elements and treats the thermo-mechanical design of the carbide pins
Key words: annular fuel elements;fuel pins;knk-2 reactor;mixed carbide fuels;performance testing;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;research programs;thermal hydraulics
R&D Category: any or undefined
display the document: 34087757.pdf
SNEAK-11: Mockup critical studies of a small sodium-cooled fast reactor SNEAK-11: Mockup-Untersuchungen fuer einen kleinen natriumgekuehlten Reaktor
Moellendorff, U. von;Helm, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P42B - German - 1980
Abstract: A series of mockup assemblies for the KNK II fast test reactor was studied in the SNEAK facility. The principal purpose was to furnish to the power reactor designers experimental data for these small, complex and asymmetric assemblies. However, it is also interesting to test the potential of different calculational methods in dealing with certain features of the assemblies. The paper presents some results on fission-rate distributions, sodium-void worth and control-rod worth
Key words: calculation methods;control rod worths;design;experimental data;knk-2 reactor;nuclear reaction kinetics;sneak reactor;sodium;spatial distribution;void coefficient;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087775.pdf
Identification of vibrational effects in KNK II fuel elements
Vaeth, W.;Mitzel, F.;Ansari, SKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3157 - English - 1981
Abstract: Several observations indicate vibrational effects in some fuel elements of the KNK-II core. This report describes how the coolant outlet temperature of each fuel element was used successfully as a means of the identification of these vibrations. As a result the cause of the sharp peaks in the power spectral density of the KNK-II reactivity noise was found. (orig.)
Key words: correlations;frequency dependence;fuel elements;knk-2 reactor;measuring methods;mechanical vibrations;neutron flux;reactivity;reactor cores;reactor noise;spectral density;temperature dependence;thermocouples
R&D Category: Commissioning and start-up testing, rise to power, transient testing
display the document: 13650951.pdf
Analysis of reactivity noise measured at KNK II with respect to vibrations of control rods and primary loop components
Mitzel, F.;Ansary, S.;Vaeth, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.))INIS-mf--8131 - English - 1981
Abstract: not available
Key words: control elements;knk-2 reactor;mechanical vibrations;primary coolant circuits;reactivity insertions;reactor noise
R&D Category: Safety aspects
display the document: 14755895.pdf
Decladding of fast breeder reactor fuel elements with lattice spaces. Die Zerlegung von Schnellbrueter-Brennelementen mit Gitterabstandshaltern
Bestenreiner, G. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))INIS-mf--10197 - German - 1981
Abstract: The method of decladding and desintegration of fuel rods is already applicable. The paper deals with the marginal conditions relevant for the desintegration (deformations, decay heat, decontamination of fuel elements), R and D work performed by INTERATOM so far and related results. The resulting courses of desintegration for SNR-300 Mk Ia or Mk II fuel elements and first practical experience made with the desintegration of KNK-II fuel elements at the KfK's hot cells are discussed. Finally a desintegration device for SNR-300 first core fuel elements designed in accordance with the aforesaid results is presented. (orig./DG)
Key words: fuel assembly dismantling;knk-2 reactor;mechanical decladding;reprocessing;snr reactor;spent fuel elements
R&D Category: Decontamination, decommissioning, disassembly
display the document: 17054134.pdf
Status of the fast breeder reactor development in the Federal Republic of Germany, Belgium and The Netherlands, February 1981
Hueper, R.;Friese, R. (Kernforschungszentrum Karlsruhe, Karlsruhe (Germany))IWGFR--37/2 - English - 1981
Abstract: In 1967 and 1968 the Federal Republic of Germany, the Kingdom of Belgium and the Kingdom of the Netherlands (DeBeNe) agreed to develop, in a joint program, breeder reactors to the point of commercial maturity. The following research organizations take part in this effort: Kernforschungszentrum Karlsruhe (KfK). INTERATOM, Bergisch Gladbach. ALKEM, Wolfgang near Hanau. SCK/CEW, Mol. Belgonucleaire, Brussels. ECN, Petten. TWO, Apeldoorn. NERATOOM, The Hague. The results of research and development activities carried out by the DeBeNe partners in 1980 have been compiled in this report. The report begins with a review of the energy policy background, followed by an R and D summary. The bulk of the report following next is organized by the Working Groups of the R and D Program Working Committee of the Fast Breeder Project. Additional chapters provide information about the operation of KNK II and the construction of SNR 300. In the annexes a survey is given of international cooperation
Key words: belgian organizations;computer codes;fbr type reactors;german fr organizations;heat exchangers;international cooperation;knk-2 reactor;netherlands organizations;reactor components;reactor cooling systems;reactor safety;research programs;snr reactor;sodium
R&D Category: any or undefined
display the document: 33018450.pdf
Core design of the second core of KNK II Kernauslegung fuer die zweite Betriebsperiode von KNK II
Spenke, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02743.4 - German - 1981
Abstract: The design report describes the behavior of the reactor core and its components during the operational period of 455 equivalent full-power days. Methods, criteria and results of the neutron physics, thermohydraulic and mechanical design are presented. By comparison of the design criteria with the results their fulfilment is demonstrated. The report also provides detailed descriptions of the operational conditions for the test-, driver-, blanket- and absorber-assemblies
Key words: breeding pellets;calculation methods;design;knk-2 reactor;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085697.pdf
Design report for core assemblies of KNK II/2: Mark II assemblies of the test zone (Central position)2.4 and 2.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Elemente der Testzone (Zentralelemente) 2.4 und 2.5
Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02749.5 - German - 1981
Abstract: The report describes the Mark II assemblies for the central position of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
R&D Category: Reactor physics
display the document: 34085698.pdf
Design report for core assemblies of KNK II/2: Driver zone assemblies without moderator Auslegungsbericht fuer Kernelemente KNK II/2: Treiberzonenelemente ohne Moderator
Bestenreiner, G.;Fenneker, K.;Ricken, E.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02750.2 - German - 1981
Abstract: The report describes the driver zone fuel assemblies without moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
R&D Category: Reactor physics
display the document: 34085699.pdf
Design report for core assemblies of KNK II/2: Mark II test zone fuel assemblies on the first ring 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 and 3.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Kranzelemente der Testzone 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 und 3.5
Bestenreiner, G.;Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04164.+ - German - 1981
Abstract: The report describes the Mark II test zone fuel assemblies of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;reactor cores;safety standards
R&D Category: Reactor physics
display the document: 34085702.pdf
Potential and state of development of acoustic boiling detection methods in sodium cooled reactors Potential und Entwicklungsstand akustischer Messverfahren zur Siededetektion in natriumgekuehlten Reaktoren
Rohrbacher, H.A.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P61A - German - 1981
Abstract: In sodium cooled reactors the application of acoustic measuring methods offers a number of new and redundant possibilities for an immediate boiling detection of the coolant. The reliability and availability of an acoustic surveillance system is substantially determined by the reactors background, the composition of the boiling spectra and their local intensity as well as by the property of the high temperature sensors. The physical process of boiling, the complex acoustic transfer function, the attenuation and delay times are described. With an assessment of the emitted acoustic energies of collapsing sodium vapour bubbles a statement is made for the absolute pressure of the acoustic signals in comparison to the experimentally measured background data of a reactor providing a realistic signal-to-noise figure. It is shown that the absolute values of acoustic pressure signals from out-of-pile boiling experiments under reactor-like conditions are in good conformity to the theoretical calculations. The choice of suitable acoustic sensors for reactor application is of great importance. The advantage and drawback of different kinds of microphones are discussed in consideration to high ambient temperatures and irradiation doses. An automatically working acoustic surveillance system of the core can be realized by an on-line-data processing system whose principal structure is described
Key words: acoustic measurements;background noise;boiling detection;bubbles;knk-2 reactor;measuring methods;on-line systems;reactor monitoring systems;sodium
R&D Category: Safety aspects
display the document: 34086292.pdf
Analysis of reactivity noise observed at KNK-II with respect to vibration of control rods and primary loop components Analyse von Reaktivitaets-Rauschen an KNK-II im Hinblick auf Vibrationen von Absorbern und Primaerkreis-Komponenten
Ansari, S.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P65A - German - 1981
Abstract: Various facts indicated that peaks in the Auto Power Spectral Density (APSD) of the neutron flux may be due to vibrations of core components. Possible candidates are the control rods. In order to scrutinize this hypothesis, seismic transducers were mounted on the shrouds of the control rod drive mechanisms of each control rod. Correlation measurements between the signals of these transducers and the neutron flux showed positive results. However from measurements with particular control rods being withdrawn from the core at zero power and from a quantitative analysis of all experimental results it must be concluded that the control rod's vibration do not cause the reactivity noise. Correlations with other signals showed that one peak of the APSD of the neutron flux is probably caused by flow induced vibrations occurring in only one of the two primary coolant loops. A possible explanation of the mechanism which causes the reactivity effects is given
Key words: control elements;control rod drives;correlation functions;knk-2 reactor;mechanical vibrations;reactor control systems;reactor noise;transducers
R&D Category: Safety aspects
display the document: 34086293.pdf
Avoidance of gas bubble caused scrams at KNK II without reducing the sensitivity of the reactimeter to bulk sodium boiling Vermeidung der an der KNK II durch Gasblasen ausgeloesten Schnellabschaltungen ohne Beeintraechtigung der Sicherheitsfunktion des Reaktimeters bei integralem Natrium-Sieden
Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P67A - German - 1981
Abstract: The KNK II was sometimes tripped by too high negative reactivity which is caused by cover gas passing through the core. Assuming that this gas entrainment is not safety relevant, these scrams may be suppressed. This paper shows, that vibrations of the tank which are observed before a gas bubble passes the core, can be used to avoid the trip: the signal of a seismic transducer triggers a dynamic modification of the reactimeter's threshold value according to a reactivity change which is typical for a gas bubble passage. Thus the reactimeter may still give a prompt trip signal, when a bulk boiling of the sodium in a fuel element occurs. Some statements concerning the reliability of the vibrational signal cannot be given quantitatively before further investigations are done
Key words: boiling detection;cover gas;entrainment;knk-2 reactor;mechanical vibrations;reactivity insertions;reactor cores;reactor safety;scram;transducers
R&D Category: Safety aspects
display the document: 34086294.pdf
Design of the grid-plate inserts of the second core of KNK II Auslegung der Gitterplatteneinsaetze fuer den zweiten Kern der KNK II (Bearbeitungsstand 02.81)
Schade, H.-JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--70.01654.9 - German - 1981
Abstract: The report describes the modified design of the grid plate inserts for the second core of KNK II together with the consequences of these changes on the plant. The changes due to the installation of special gas bubble separators in the 30 grid plate inserts of the sixth fuel element row have the goal to assure a plant operation, which is not disturbed by gas bubble transport through the core and the consequent reactivity effects. The detailed construction and the experimental verification of the concept are described. Further explanations are related to the thermal-hydraulic design of the second KNK II core with special consideration of the new flow scheme, to the reactivity behaviour of the core in case of gas bubble ingress and to the plant behaviour in case of disturbations, especially the emergency cooling situation. It is proved that the sufficient cooling of the core is guaranteed and that the safety degree of the plant is not deteriorated by the design modifications
Key words: bubbles;eccs;entrainment;fluid flow;fuel elements;knk-2 reactor;reactivity insertions;reactor operation;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087405.pdf
KNK II, Safety Report for the second core, following cores and the test program KNK II, Sicherheitsbericht fuer den zweiten Kern sowie Folgekerne und das Versuchsprogramm
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--75.1438.5 - German - 1981
Abstract: In the first core of KNK II with its extended residence time of 400 equivalent full-power days the fuel subassemblies of the SNR 300 first core with 6.0 mm outer diameter had been operated successfully. Accordingly, it was planned to irradiate subassemblies of the SNR 300 second core type with 7.6 mm fuel pins in the second core of KNK II. Additionally, the option for further variations in later cores should be kept open. With the example of the transition from the first core of KNK II to the second one, the present safety report describes possible changes and proves their compatibility with the design criteria. The changes concern the reactor core and its components, the reactor instrumentation and plant protection system, the radiation protection measures and the safety and accident analysis. The continued experimental program is also illustrated with its irradiations of fuel subassemblies, absorber assemblies and structural materials and with the tests related to the reactor instrumentation and chemical test procedures
Key words: knk-2 reactor;reactor cores;reactor licensing;reactor protection systems;reactor safety;research programs;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087408.pdf
Description of the KNK II first core und its assemblies for an extended residence time of 400 equivalent full-power days Beschreibung des KNK II Erstkerns und seiner Elemente fuer eine verlaengerte Standzeit von 400 Vollasttagen
Schade, H.J.;Toebbe, H.;Wehmann, UINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--54.04231.0 - German - 1981
Abstract: The present report describes the performance of the whole core, the assemblies and their pins for an extended residence time of the first core until 400 equivalent full-power days. The extension can be realized by making use of the reactivity reserve of the present core and by loading of reserve fuel assemblies. The report contains the neutron physical, thermal-hydraulical and mechanical operational data of the core and its assemblies for the nominal operation and in case of emergency cooling. It also presents the operational and accidental dynamic behavior of the core and the heat transfer circuits and aspects of fuel assembly disposal
Key words: burnup extension;eccs;heat transfer;knk-2 reactor;reactor accidents;reactor cores;reactor kinetics;thermal hydraulics
R&D Category: any or undefined
display the document: 34087411.pdf
PNC/CEA/DEBENE specialists' meeting on LMFBR plant experience, Cadarache, FRANCE, October 1981
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-PSB--066 - English - 1981
Abstract: The present report compiles four German papers presented at the Cadarache exchange meeting on the JOYO/ RAPSODIE/ KNK plant experience. After an overview on the situation at KNK II, papers on 'Detection, localization and post-irradiation examination of failed fuel elements', 'Measurements and interpretation of physics coefficients at KNK II' and 'Current status of gas entrainment problem' are documented
Key words: entrainment;failed element detection;fuel element failure;knk-2 reactor;post-irradiation examination;reactivity coefficients;reactor kinetics;reactor operation;safety analysis
R&D Category: any or undefined
display the document: 34087497.pdf
Power operation start-up of the compact sodium-cooled nuclear power plant KNK II/1 Leistungsinbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II/1
Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
INIS-DE-KBG--008 - German - 1981
Abstract: This report describes the power start-up phase of the first fast core of KNK II up to nominal power. The results of reactor physics, thermohydraulics and plant engineering measurements were compared with design data. On the plant side a restart of the systems was performed, which had been proven during the KNK I operation. Up to 40 % power the temperature rise was built up with constant mass-flow, while between 40 and 100 % the mass-flow was increased with constant temperature rise. As fixed in the functional test program F4, the important plant parameters, such as thermal power, radial power distribution, reactivity coefficients and dose rates, were determined. Additionally, investigations were performed to optimize control processes and safety related installations, such as the reactor control or the decay heat removal behavior
Key words: after-heat removal;dose rates;knk-2 reactor;power distribution;reactivity coefficients;reactor control systems;reactor operation;reactor start-up;thermal hydraulics
R&D Category: Reactor physics
display the document: 34087481.pdf
KNK - annular fuel element with carbide test bundle: Estimation of the sodium outlet temperature in case of obstruction of the test bundle, respectively the annular carrier element KNK - Ringelement mit 19-Stab Karbid-Testbuendel: Abschaetzung der Natriumaustrittstemperatur bei Verstopfung von Testbuendel bzw. Ringelement
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P62B - German - 1981
Abstract: For KNK II an annular carrier element with an integrated 19-pin carbide test bundle is planned to be placed on a ring position of the test zone. With regard to safety aspects, the effects of obstruction in, both, the annular element and the test bundle on the sodium outlet temperature were studied. It was found that a 60 % reduction of mass flow in the test bundle leads to a temperature increase behind the mixing device of 26 K. This value has been suggested as a limit for reactor scram in order to obviate the possibility of sodium boiling in the test bundle. For the annular element the same value already leads to reactor scram at 16 % mass flow reduction
Key words: annular fuel elements;flow blockage;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;temperature distribution;thermal hydraulics
R&D Category: Reactor physics
display the document: 34087758.pdf
Technical specifications for the fuel pin of the carbide element in the test zone of KNK II/2 Technische Spezifikationen fuer den Brennstab des Karbidelementes der Testzone von KNK II/2
Freund, D.;Jacobi, O.;Ritzhaupt-Kleissl, H.-J.;Steiner, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.16P66A - German - 1981
Abstract: Uranium-Plutonium-Mixed Carbide fuel is investigated as an alternative fast breeder fuel to the actual mixed oxide because of some special properties. As a completion of the carbide irradiation program of KfK/PSB the operation of a 19-pin bundle in KNK II was foreseen. On the basis of the national and international experience a reference concept was defined for that purpose. Among others, the following data were fixed: pin diameter 8.5 mm, clad thickness 0.55 mm, fuel smear density 75 %, He-bonding, maximum nominal linear rating 800 W/cm. The present report contains the specifications for the fuel pin including fissile and fertile materials as well as for structural materials. The fuel pins fabricated according to these specifications will guarantee the expected operational behavior
Key words: design;fertile materials;fissile materials;fuel assemblies;fuel pins;knk-2 reactor;mixed carbide fuels;specifications
R&D Category: any or undefined
display the document: 34087771.pdf
Measurement of the fission rate distribution in SNEAK 11B2 Messung der Spaltratenverteilung in SNEAK 11B2
Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P62A - German - 1981
Abstract: The report describes the fission rate measurements performed in SNEAK 11B2, which is the simulation of the fresh first reload core of KNK II. It contains all measured values. Comparisons with calculated values have already partly been reported previously
Key words: experimental data;knk-2 reactor;reactor cores;reactor fueling;sneak reactor;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087777.pdf
Fuel reprocessing of the first failed KNK-II fuel element in MILLI. Die Wiederaufarbeitung von Brennstoff aus dem ersten defekten KNK II-Brennelementen in der MILLI
Bleyl, H.J. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Heisse Chemie)KFK--3278 - German - 1982
Abstract: In MILLI reprocessing of fuel from 32 KNK II-pins was carried out. 3 extraction cycles were applied: co-decontamination, U-/Pu-separation and purification of uranium. The products were shipped to refabrication of KNK II fuel by Nukem and Alkem companies. (orig.)
Key words: fuel element failure;fuel pins;knk-2 reactor;purex process;solvent extraction
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695220.pdf
Experience on fuel recycling. Erfahrungen zur Brennstoff-Rezyklierung
Schneider, V.;Druckenbrodt, W.G. (Alpha Chemie und Metallurgie G.m.b.H.)KFK--3278 - German - 1982
Abstract: The plutonium of the second generation out of the KNK-reactor will be converted at the fuel fabrication by ALKEM by the Au/PuC process. The preliminary tests for the fabrication have been finished and two batches were converted. Up to now the results show no principal difficulties. (orig.)
Key words: fuel fabrication plants;knk-2 reactor;plutonium recycle
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695223.pdf
KNK-II fuel elements and their operational behavior. Die Brennelemente der KNK-II und ihr Betriebsverhalten
Mayer, H. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.));Richard, H. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.))KFK--3278 - German - 1982
Abstract: Design, fabrication, authorization for operation and the operation itself signify for the project partners involved the step from an research and development program to the procurment of a larger number of fuel subassemblies for a nuclear power plant. Although priority is given to operations experience, those assemblies have to be part of the long-term fuel development program. The first fast core of the KNK-II has reached a residence time of 273 efpd corresponding to a peak burnup of 65.000 MWd/tsub(HM) in 5 assemblies. By such, the originally planned target of 255 efpd has already been exceeded. The authorization for an operation up to 355 efpd has been granted. The extended periods of operation at 100% load as well as the reached burnup prove that the two fuel pin defects (in two assemblies one pin each) do not have any systematic origin. (orig.)
Key words: burnup;fuel element failure;fuel elements;fuel pins;knk-2 reactor;performance;reactor operation
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 13696676.pdf
The reference concept of the KNK-2 back end fuel cycle. Das Referenzkonzept zur Entsorgung der KNK II
Schnetgoeke, G. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)KFK--3278 - German - 1982
Abstract: The reference concept of the KNK back end fuel cycle ensures the provisions required by the legislator. According to this concept the spent fuel subassemblies are stored in the KNK subassembly storage facility for about 9-12 months in order to remove the decay heat before they are freed from the attached sodium in a scrubbing step and subsequently packed into special subassembly cans. The loaded cans are transferred to the MZFR reactor whose fuel subassembly storage facility is being modified in order to be capable of accepting two KNK-II core charges. By this intermediate storage facility the waiting periods are bridged between the withdrawal of the subassemblies from KNK and the singulizing in the Hot Cells. After singulization the fuel rods are packed into fuel rod cans which differ greatly from the subassembly cans as regards their geometry. Following another intermediate storage of the dismantled subassemblies in the MZFR reactor two core charges will be transported to Marcoule in 1986 and reprocessed there. The products will be returned as plutonium oxide and uranyl nitrate. (orig.)
Key words: fuel cycle;fuel storage pools;knk-2 reactor;spent fuel elements;spent fuel storage
R&D Category: any or undefined
display the document: 13696677.pdf
Sodium removal from fuel elements. Die Entfernung des Natriums von Brennelementen
Stade, K.C.;Breitlaender, H. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.));Stamm, H.H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Radiochemie)KFK--3278 - German - 1982
Abstract: The steam-nitrogen method was used for the sodium removal from undamaged KNK-I fuel elements. 66 fuel bundles (= 2904 fuel pins) with an average burn-up of 5800 MWd/tsub(HM) were cleaned using this method, four to six months after the final shut-down, during the time from December 1974 to February 1975. The sodium removal was complete. No defects originated from the cleaning procedure. The sodium removal from KNK-II and SNR-300 fuel without cladding failures will be accomplished by the same process. At KNK-II, the existing plant has to be modified before KNK-II elements may be treated. So far, two defective fuel elements (burn-up 17400 MWd/tsub(HM), and 48000 MWd/tsub(HM), respectively) have been removed from the KNK-II core. The limited sodium removal achieved by blowing with hot argon was sufficient for the following dismantling of these bundles in the KfK hot cell laboratories. (orig.)
Key words: argon;blowers;fuel washers;knk-2 reactor;purification;sodium;spent fuel elements
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13696678.pdf
Dismantling and post-irradiation examination of the two first defective fuel pins of the KNK-II. Die Zerlegung und Nachuntersuchung des ersten und zweiten defektiven KNK II-Brennelemente
Enderlein, H.;Kathol, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Hauptabteilung Kerntechnische Betriebe;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)KFK--3278 - German - 1982
Abstract: The report contained the dismantling and the post irradiation examination of the two first defective fuel elements of the KNK II-reactor. The construction of the dismantling device and the process of dismantling of the fuel elements are described. The main aim of the examination of the fuel pins is to find the defective pin and to establish the cause of the pin damage. The most important steps for this are shown, also a few of the results. Finally improvements