Component Category: -Core components
65 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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
Vibrational effects of fuel elements detected during KNK II power operation
Mitzel, F.;Vaeth, W.;Ansari, SKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P85B - English - 1982
Abstract: The reactivity signal of the KNK II reactor shows almost harmonic reactivity oscillations of
Key words: flow stress;fuel elements;knk-2 reactor;mechanical vibrations;performance testing;reactivity;vortex flow
R&D Category: Safety aspects
display the document: 34086295.pdf
Test operation KNK II: Investigation of the gas entrainments with disengaged reactivity limit (May '81 till Febr. '82) Versuchsbetrieb KNK II: Untersuchung von Gasdurchlaeufen bei abgeschaltetem Reaktivitaetsgrenzwert (Mai '81 bis Febr. '82)
Becker, M.;Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
KBG--UP0382.1 - German - 1982
Abstract: During the start-up phase of KNK II the reactor was tripped repeatedly by signals of too negative reactivity, which were caused by gas entrainment. In the frame of a special test program a limited power operation campaign was performed in which the reactivity threshold of the reactimeter was deactivated in order to study the pattern and the amplitudes of the reactivities in the power range of 40 to 90 %. The report describes the course of the test program and its results. All together 22 signals were observed exceeding the threshold of -7.3 cent with a largest peak of -19 cent. An influence of the reactor power could not be observed, but a general difference compared with the operation in 1979/80 could be noted after the mass-flow reduction in the degasification pipe. Probably the discharge mechanism of the gas storage has been changed, but no new knowledge about the storage localization could be gained
Key words: entrainment;gases;knk-2 reactor;power distribution;reactivity;reactor operation;reactor start-up
R&D Category: Safety aspects
display the document: 34087735.pdf
Several neutron-physical aspects of modified KNK-II assemblies. Einige neutronenphysikalische Aspekte modifizierter KNK II-Anordnungen
Broeders, I.;Krieg, B.;Kuesters, H.;Stein, E. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)KFK--3543 - German - 1983
Abstract: These surveys aim at designing KNK II reloads with fuel that is as prototypical as possible, i.e. mixed oxide fuel of a U-235 enrichment that is as low as possible and also at examining related neutron-physical aspects. In these reloads emphasis is also put on good experimenting conditions. Neutron-physical calculations for the examined reload cores were carried out using the three-dimensional diffusion programme D3E with
Key words: enriched uranium;knk-2 reactor;mixed oxide fuels;neutron diffusion equation;neutron flux;neutron reactions;reactor physics
R&D Category: Reactor physics
display the document: 15028466.pdf
KNK-II reactor: Reload experiments in SNEAK-11 reactor. KNK II: Experimente in SNEAK 11 zu Nachladungen
Moellendorff, U. v. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)KFK--3543 - German - 1983
Abstract: Three reload cores originally planned for the KNK-II reactor were examined at the Karlsruhe Fast Zero Energy Assembly (SNEAK-reactor) under the denomination of SNEAK 11. Two of them were assembled in two versions each: with drawn absorber rods, i.e. corresponding in its criticality with spent power reactors, which is the normal SNEAK assembly. And with absorbers half-inserted as with new cores. The latter of the two in closer to the actual core design task, yet it causes great calculation problems, because they need to be mainly three-dimensional. Main points of the measuring programme included: - critical sizes (with drawn absorbers) or critical insertion depth of the KNK control/scram absorbers, - fission rate distribution, - sodium loss reactivity, - absorption values of control/scram rods and secondary shutdown units. (orig./RW)
Key words: control rod worths;criticality;knk-2 reactor;reactor kinetics;reactor lattice parameters;reactor physics;sneak reactor
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 15028467.pdf
Design of the second core of KNK II Auslegung des zweiten Kerns der KNK II
Schade, H.-JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--70.02244.0 - German - 1983
Abstract: In the first core of KNK II with its extended residence time of 400 equivalent full-power days the Mark Ia fuel elements of the first core of SNR 300 with 6.0 mm outer diameter were successfully tested. The mission of the second core of KNK II was accordingly to irradiate the Mark II elements of the first reload of SNR 300 with 7.6 mm fuel pins. Additionally, some irradiations of the first core should be continued and new ones should be started. The present report describes first the design of the reactor core and the core assemblies together with the planned irradiation experiments. Subsequently the irradiation protection situation under nominal and accidental conditions is discussed and the reactor protection system with its modifications for the second KNK II core is described. Finally, the results of accident analysis are explained, with which the safety related proofs for the operation with the modified core are delivered
Key words: design;irradiation;knk-2 reactor;reactor cores;reactor protection systems;reactor safety;risk assessment;safety analysis;snr reactor
R&D Category: any or undefined
display the document: 34087406.pdf
Nuclear, thermal-hydraulic and mechanical investigations of different variants for the third core of KNK II Nukleare, thermohydraulische und mechanische Untersuchungen zu verschiedenen Varianten des dritten Kerns der KNK II
Wehmann, UINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--54.05674.4 - German - 1983
Abstract: The present report describes the results of nuclear, thermal-hydraulic and mechanical investigations for the core design of different variants of the third core of KNK II. These were: Variant 1 like the first core, Variant 2 like the second core, Variant 3 as mixed-oxide core with 7.6 mm fuel pins, Variant 4 as Uranium oxide core with 7.6 mm fuel pins and Variant 5 as mixed-oxide core with 8.5 mm fuel pins. The investigations have shown, that from core design point of view all variants are technically feasible, that they would assure normal operation and would leave about similar flexibility for the test program. With respect to the intermediate and long-term relevance of the fuel assemblies to be used, the transition to the 8.5 mm fuel pins is to be recommended. In order to have an as large as possible number of standard assemblies in parallel to the non-standard assemblies in the core, the present test zone is recommended to be extended by the 6 unmoderated driver positions. In order to realize the wanted reduction of absorber positions, the more favourable absorber pin design (pressureless, thicker pins) should be chosen
Key words: design;fuel assemblies;knk-2 reactor;mechanical properties;mixed oxide fuels;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: any or undefined
display the document: 34087412.pdf
Study of definition: Investigation of different variants for the third core of KNK II Definitionsstudie KNK II/3: Untersuchung verschiedener Kernvarianten fuer einen dritten Kern der KNK II
Schade, H.-J.;Toebbe, H.;Wehmann, UINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--54.05817.2''A'' - German - 1983
Abstract: The present report describes the results of investigations, which were performed at INTERATOM at the request of the KfK Karlsruhe on different versions for the third core of KNK II. These variants were: Variant 1 like the first core, variant 2 like the second core, variant 3 as mixed oxide core with 7.6 mm fuel pins, variant 4 as Uranium oxide core and variant 5 as mixed oxide core with 8.5 mm fuel pins. Furthermore statements about a possible reduction of the number of absorber positions had to be done. The investigations concerning the core design, fuel assembly and fuel pin design, operational and accidental behavior, radiology and shielding revealed the following main results: 1. All investigated variants are technically feasible, guarantee the normal operation and give the test operation similar flexibility. 2. No major licensing problems are to be expected, whereby detailed problems will require special proofs. 3. The number of absorbers could be reduced by one, but a more favourable absorber pin design (pressureless, thicker pins) should be chosen. 4. In view of a gain in experience for future breeder reactors, a core with 8.5 mm fuel pins is recommended
Key words: design;feasibility studies;fuel assemblies;fuel pins;knk-2 reactor;licensing regulations;mixed oxide fuels;neutron absorbers;reactor cores;safety analysis;shielding;uranium oxides
R&D Category: any or undefined
display the document: 34087413.pdf
Legend and operational data of KNK (March 1966 until Dec. 1982) Legende und Betriebsdaten der KNK (Maerz 1966 bis Dez. 1982)
Alfke, H.-W.;Richard, H.;Streib, K.-PhKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--002 - German - 1983
Abstract: This report first describes the KNK I plant with thermal core with its operational phase from 1966 until 1974 and the reconstruction to KNK II with fast core including the authorities' licenses. Subsequently the KNK II plant with its first fast core is described and the operational legend is detailed including the start-up program. The operational results until December 1982 contain the energy production, fuel balance and irradiation protection aspects
Key words: fast reactors;knk-2 reactor;power generation;radiation protection;reactor cores;reactor operation;reactor start-up;thermal reactors
R&D Category: any or undefined
display the document: 34087477.pdf
Overview of the design of core restraint systems
Heinecke, J. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--54 - English - 1984
Abstract: The optimization of the core restraint system is an important condition for the safe and reliable operation of a fast breeder reactor. For KNK II which is under successful operation and SNR 300 all requirements for safety and operation have been met with help of a ring type system. For SNR 2 the decision between the ring type system and the free standing core has to be done in the near future. Within these considerations the advantages of a ring type restraint system of limiting deflections during operation and limiting of possible movements under seismic conditions have to be balanced against the somewhat more complicated structure of the ring type restraint system
Key words: computerized simulation;knk-2 reactor;reactor core restraints;snr reactor;snr-2 reactor;specifications
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 18010132.pdf
Operational tests at zero power and at power of the second core of the compact sodium cooled power plant KNK II Funktionspruefungen bei Nulleistung und Leistung des Kerns II/2 der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II
Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
KBG--UP0384.2 - German - 1984
Abstract: This report describes the nuclear start-up phase of the second core of KNK II at zero power and up to nominal power. The first criticality was achieved on June 26th, 1983 and full power was reached two months later. The results of reactor physics, thermal-hydraulics 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 first core operation. During the whole start-up phase no disturbing or unforeseen events were observed. The measured parameters (critical mass, control rod worths, reactivity coefficients, temperature rise distributions) agreed well with the results of the pre-calculations within the error intervals
Key words: comparative evaluations;control rod worths;critical mass;experimental data;knk-2 reactor;reactivity coefficients;reactor operation;reactor physics;reactor start-up;temperature distribution;theoretical data;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087736.pdf
Final Report about the gas bubble problem in KNK II Abschlussbericht zum Gasblasenproblem der KNK II
Richard, H.;Schade, H.-JKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH, Bergisch Gladbach (DE)
KBG--UP1084.2 - German - 1984
Abstract: During the operation of the first core of KNK II repeatedly reactor scrams occurred above a power level of about 60 %, which were initiated by the reactivity limit of -7.3 cent. The scrams were caused by discontinuous gas bubble passages through the core, which lead to peak-like reactivity reductions. In experiments at the plant and in models possible sources of the gas ingress and of gas storages were investigated and identified. As ingress source the degassing line and the primary pumps were identified. The ingress by the degassing line could be eliminated by technical modifications, and the additional ingress via the pumps was found to be so small, that no modifications were performed. The investigations pointed with rather large probability to the annular area besides the grid-plate as the storage of the gas. As solution for the second core of KNK II the flow path towards the reactor core was changed by a modification of the grid-plate inserts. By this means, possible gas quantities are diverted around the core through the reflector assemblies without causing reactivity effects, and the suspected storage in the annular area is eliminated. During the start-up of the second core it was shown, that the gas bubble problem of the first core has been completely eliminated, and this result was fully confirmed by the power operation of KNK II/2
Key words: bubbles;degassing;entrainment;fuel elements;gases;knk-2 reactor;reactivity insertions;reactor cores;reactor operation;scram
R&D Category: Safety aspects
display the document: 34087737.pdf
Design report for the residence time extension of KNK II/2 from 455 to 720 equivalent full-power days Auslegungsbericht fuer die Standzeitverlaengerung der KNK II/2 von 455 bis 720 Vollasttage
Schade, H.-J.;Steinmetz, B.;Wehmann, UINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06665.7 - German - 1985
Abstract: The report describes the performance of the whole reactor and of its assemblies and their components during the residence time extension of the second core of KNK II from the foreseen value of 455 equivalent full-power days (efpd) to 720 efpd. By this extension existing reactivity and design reserves can be utilized, and the burnup of the test zone assemblies can be increased towards the level aimed at for future sodium breeder reactors. The investigations about the static and the dynamic behavior of the core with its components and of the heat transfer systems under nominal and accidental conditions show, that the plant can be safely operated during the residence time extension
Key words: burnup extension;design;heat transfer;knk-2 reactor;reactor cores;reactor kinetics;safety analysis
R&D Category: Reactor physics
display the document: 34085707.pdf
Characteristics of the KNK II second core-- irradiation history, power tilting campaign, subassembly reloadings, failed fuel detection and burnup data (358/758 VLT), status of October 10th,1985. Charakteristik der KNK II Zweitbeladung, Bestrahlungsverlauf, Elementwechsel, Schieflastbetrieb, Defektsuche und Abbranddaten (358/758 VLT), Stand 10.10.1985
Geier, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06820.8 - German - 1985
Abstract: The report gives an overview of the KNK II operation until October 10th, 1985. Additionally, the development of the second fuel pin failure, the flux tilting campaign and the failed fuel detection are described. Until October 1985 the high-burnup subassembly, which was already operated in the first core of KNK II for 400 equivalent full-power days, achieved a maximum local burnup of 161 MWd/t(HM) or 17 at.% and the subassemblies of the second core reached 53 MWd/t(HM) or 5.6 at.%. The corresponding steel displacements are 61.8 and 22.4 dpa-NRT, respectively
Key words: atomic displacements;burnup;failed element detection;fuel element failure;fuel management;knk-2 reactor;neutron flux tilting;reactor operation
R&D Category: Reactor physics
display the document: 34085709.pdf
Design Report for the third core of KNK II (KNK II/3) Auslegungsbericht fuer den dritten Kern der KNK II (KNK II/3)
Stanculescu, AINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06990.0 - German - 1986
Abstract: The report describes the behavior of the third core of KNK II (KNK II/3) during the foreseen residence time of 720 equivalent full-power days. Methods, criteria and results of the neutron physical, thermal-hydraulic and core mechanical design are presented. The fulfilment of the criteria is proved by the comparison with the calculational results. Additionally, the conditions for the operation of the different test-, driver-, breeder- and absorber-elements are described
Key words: design;fuel assemblies;hot channel factor;hot spot factor;knk-2 reactor;mechanics;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085716.pdf
Decay heat and activity of the structural materials of the fuel and blanket assemblies of the second and third core of KNK II Nachzerfallsleistung und Aktivitaet aus den Strukturmaterialien der Brenn- und Brutelemente der KNK II Kerne 2 und 3
Winterhagen, DINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--70.03765.0 - German - 1986
Abstract: The decay heat and activity caused by structural materials have been calculated for the fuel assemblies of KNK II (second and third core) with a residence time of 720 equivalent full-power days (efpd) and the blanket assemblies with 1880 efpd. The values are given for the different zones of the assemblies (head, active zone, fission gas plenum, foot and stellite area) for decay times from 1 to 20 years. For decay times beyond 2 years more than 80 % of the decay heat are caused by the Co60-decay, more than 60 % of which result from the stellite in the foot area
Key words: after-heat;breeding blankets;cobalt 60;fuel assemblies;knk-2 reactor;radioactivity;reactor cores
R&D Category: Reactor physics
display the document: 34087390.pdf
Safety related investigations for the third core of KNK II with a residence time of 720 equivalent full-power days (part B) Sicherheitstechnische Untersuchungen fuer den dritten Kern der KNK II mit einer Standzeit von 720 Vollasttagen (Teil B)
Becker;Stepan;WinterhagenINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.03907.7 - German - 1986
Abstract: The present report describes safety related investigations for the third core of KNK II with a residence time of 720 equivalent full-power days (efpd). The following aspects have been considered: Decay heat of the core assemblies, core temperatures in case of emergency cooling, primary shielding with shielding of the handling facilities, radioactive materials in the plant and radiological affects on the environment in case of nominal operation and of accidents. In comparison with the second core with its residence time extension to 720 efpd, the results do not show unacceptable changes
Key words: after-heat removal;burnup extension;eccs;fuel cycle;knk-2 reactor;radiology;reactor accidents;safety analysis;shielding;steady-state conditions
R&D Category: Safety aspects
display the document: 34087391.pdf
KNK II, Safety Report for the residence time extension of the second core to 720 equivalent full-power days KNK II, Sicherheitsbericht fuer die Standzeitverlaengerung 2. Kern auf 720 Vollasttage
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA--75.15917.* - German - 1986
Abstract: The second core of the compact sodium-cooled power plant KNK was licensed for a residence time of 455 equivalent full-power days (efpd). During the operation it became clear, that the use of the reactivity reserves in the core and by loading some additional fuel elements would allow a residence time extension without violation of design criteria. An extension to 720 efpd was applied for, and the present safety report is part of the corresponding application documents. The report describes the design of the core and its components, the reactor instrumentation and plant protection system, the radiation protection measures, the safety and accident analysis as well as the continued experimental program. It is shown that the frame of the KNK II safety report, provided in 1973, is still kept
Key words: burnup extension;design;knk-2 reactor;licensing;radiation protection;reactor cores;reactor safety;research programs;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087396.pdf
Short description of the residence time extension for KNK II second core to 720 equivalent full-power days Kurzbeschreibung der Standzeitverlaengerung KNK II zweiter Kern auf 720 Vollasttage
Richard, H.;Schmidt-Hoenow, MINTERATOM GmbH Bergisch-Gladbach (Germany), Kernkraftwerk-Betriebsgesellschaft mbH (DE), Kernforschungszentrum Karlsruhe GmbH (DE)
IA--75.15918.1 - German - 1986
Abstract: The second core of KNK II was licensed for a residence time of 455 equivalent full-power days (efpd). Since it became obvious during the operation, that the core contained sufficient reactivity reserve, a residence time extension of up to 720 efpd was applied for. The present short description as part of the application documents describes the reactor core with the core elements and the continuation of the test program. Subsequently the plant safety systems, the irradiation protection and the waste disposal are outlined
Key words: burnup extension;knk-2 reactor;reactivity;reactor licensing;reactor operation;reactor safety;research programs
R&D Category: any or undefined
display the document: 34087397.pdf
Operation of KNK with defective fuel assemblies and consequences to be drawn. Presentation at the Exchange Meeting about the operation of KNK II and BOR 60/BR 10 Plants, Dimitrowgrad, September 5.- 8., 1988 Betrieb der KNK mit schadhaften Brennelementen und Konsequenzen daraus. Praesentation auf dem Meeting zum Erfahrungsaustausch ueber den Betrieb von KNK II und BOR 60/BR 10 Anlagen in Dimitrowgrad, 5. - 8. September 1988
Steiger, WKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--014 - German - 1986
Abstract: The paper illustrates the operational history of KNK II with its first two core loadings with 400 equivalent full-power days (efpd) for the first loading and 455 efpd for the second loading. During this period of 855 efpd eight fuel failures occurred. These failures had been detected by different means, such as radioactivity of the cover gas, delayed neutron detection or the ratio of the Xe131 and Xe134 concentration. The paper explains the type of failures and the lessons learned and consequences drawn from these failures
Key words: failed element detection;failed element monitors;fuel cycle;fuel element failure;isotope ratio;knk-2 reactor;reactor operation;reactor safety;xenon 131;xenon 134
R&D Category: Safety aspects
display the document: 34087484.pdf
Irradiation capsule with heat pipes for KNK II and SNR 300 Bestrahlungskapsel mit Waermerohr fuer KNK II und SNR 300
Mueller, K.;Bojarsky, E.;Norajitra, P.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-PSB--061 - German - 1986
Abstract: A novel irradiation capsule with self-acting temperature control was developed for irradiation of specimens in material testing elements, not amendable to instrumentation, of the KNK II and SNR 300 reactors. The capsule is equipped with a gas-buffered heat pipe, which, acting as a heat transfer system, guarantees maintaining the desired specimen temperatures also under conditions of reactor power variations and major deviations from the design values. The heat pipe is arranged in the center of a cylinder with external heat insulation. The annulus is filled with material specimens which are brought to elevated temperatures through gamma-heating. Sodium serves as the heat transfer fluid in the heat pipe. In 1985 a prototype capsule was irradiated successfully at the KNK II over an extended period of time. The design temperature of 650 deg C was attained with high accuracy. It is planned to irradiate the capsules in the SNR 300 reactor at the same temperature level
Key words: heat pipes;heat transfer;irradiation capsules;irradiation;knk-2 reactor;radiation heating;snr reactor;temperature dependence;temperature monitoring
R&D Category: any or undefined
display the document: 34087495.pdf
Results of acoustic measurements with an electric boiling generator at KNK II Ergebnisse der akustischen Messungen mit einem elektrischen Siedegenerator in der KNK II
Aberle, JKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.19P16A - German - 1987
Abstract: With regard to an integral core surveillance in sodium-cooled breeder reactors acoustic measurement techniques are under development. To determine experimentally the acoustic transfer function of a reactor core and to demonstrate the detectability of local sodium boiling, experiments with a so-called Boiling Generator were carried out in the KNK II reactor. The main part of this Boiling Generator was an electrically heated pin bundle which was equipped with a local blockage to obtain cooling disturbances. In this report the results of the acoustic measurements carried out with the Boiling Generator are presented. Main topic of the evaluation is the determination of the acoustic transfer function between the core and the upper sodium plenum. The signal conditioning necessary prior to this investigation is also explained. Great effort was required to suppress electrical disturbances which superimposed the acoustic signals and could not be eliminated by the hardware during the experiments. Finally, the detectability of local boiling using acoustic measurements is considered
Key words: acoustic measurements;boiling detection;flow blockage;knk-2 reactor;reactor cooling systems;reactor cores;signal conditioning;sodium;transfer functions
R&D Category: Safety aspects
display the document: 34086296.pdf
Determination of static and dynamic reactivity effects in KNK II Ermittlung statischer und dynamischer Reaktivitaetseffekte in der KNK II
Essig, CINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.04123.3 - German - 1987
Abstract: In the frame of a pre-study of the KNK II test program two series of experiments related to inherent safety characteristics of sodium cooled breeder reactors have been elaborated, which are one basis for the performance of experiments of the Loss Of Flow (LOF) type and the Loss Of Heat Sink (LOHS) type. Tests of this type at KNK II would -different from the earlier tests at RAPSODIE and EBR-II- provide a demonstration of the inherently safe performance in case of a significantly non-zero Doppler effect. With a suitable execution, the foreseen series of experiments allow, as explained in this report, a substantial separation of the reactivity contributions and the determination of reactivity effects, i.e. the time constants of the recouplings. The performance and evaluation of these experiments with respect to the inherent safety potential will once more underline the distinguished role of KNK II for the development of fast breeders
Key words: doppler effect;dynamics;feedback;knk-2 reactor;loss of flow;reactivity;reactor safety experiments;risk assessment;testing
R&D Category: Reactor physics
display the document: 34087392.pdf
Legend and operational data of KNK II in the period 1983-1986 Legende und Betriebsdaten von KNK II in der Periode 1980-1986
Alfke, H.-WKernkraftwerk-Betriebsgesellschaft m.b.H. (Germany)
INIS-DE-KBG--001 - German - 1987
Abstract: This report describes the KNK II legend for the period 1983-1986 together with the operational data for the areas fuel, energy production and energy supply, availability and radiation protection. The documentation starts with the preparation and the loading of the second core of KNK II. For the better understanding of tables and figures, data of the terminated KNK II first-core operation are also included
Key words: energy supplies;knk-2 reactor;power generation;reactor cores;reactor operation
R&D Category: any or undefined
display the document: 34087476.pdf
KNK II, third core: Design Report of the reactor core KNK II, dritter Kern: Auslegungsbericht fuer den Kern
Timm, WINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07541.* - German - 1988
Abstract: The report describes the behavior of the KNK II/3 whole reactor core during its foreseen residence time of 720 equivalent full-power days. Design methods, criteria and results of the neutron physics, thermal-hydraulics and mechanical design are described. The respectation of the design criteria is proved by their comparison with the results. Additionally, the operational conditions are described for the different test-, driver-, breeder- and absorber-assemblies
Key words: breeding pellets;calculation methods;design;knk-2 reactor;mechanics;neutron absorbers;reactor cores;thermal hydraulics
R&D Category: Reactor physics
display the document: 34087380.pdf
Computer program Schieflast Rechenprogramm Schieflast
Timm, WINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.07594.3 - German - 1988
Abstract: For the analysis of flux-tilting experiments for the detection of defective fuel assemblies in KNK II the computer program SCHIEF has been developed. It analyses the flux-tilting campaigns only on the basis of measured delayed neutron signal changes and the control rod bank position of the reference state. All other dates, such as absorber position and local power changes for the different flux-tilting campaigns, are calculated code-internally. Hereby, neutron physics data of three-dimensional calculations are used. With the help of SCHIEF all flux-tilting campaigns performed during the KNK II/2 operation have been analysed supplementarily. For each flux-tilting campaign three to four suspicious fuel assembly positions with defects were found, whereby the previous evaluation procedures were confirmed essentially. The flux-tilting campaign at 403 equivalent full-power days remains unclear, since there is no indication in the analysis on the defect on position 203. An analysis with the assumption of two defects does not provide reliable hints on possible positions of the defects
Key words: computer program documentation;control elements;delayed neutrons;failed element detection;knk-2 reactor;mathematical models;neutron flux tilting;s codes
R&D Category: -Failure detection
display the document: 34087383.pdf
KNK II/2: Results of the evaluation of neutron physics operational data KNK II/2: Ergebnisse der neutronenphysikalischen Betriebsverfolgung
Stanculescu, A.;Haan, E. deINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07586.3 - German - 1988
Abstract: This report describes the important results of neutron physics calculations (keff, power distribution, burnup, mass balances and dose values) which accompanied the operation of KNK II/2, with status of June 1988. Additionally, the results of calculations for the period beyond the actual status and beyond the licensed operation period with the residence time extension from 455 to 720 equivalent full-power days are documented
Key words: burnup;computer calculations;knk-2 reactor;multiplication factors;power distribution;reactor physics
R&D Category: Reactor physics
display the document: 34087382.pdf
KNK II, third core: Project-Material-Data-Handbook IV, Revision status 04/88 KNK II, 3. Kern: Projekt-Materialdatenhandbuch IV, Revisionsstand 04/88
Bergmann, H.-JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--55.07148.1.B - German - 1988
Abstract: The report contains the material data sheets and design formulae of the cladding materials and structural materials of the core area to be used in the design of the third core of KNK II. The data are given for the materials 1.4970 kv (X10CrNiMoTiB 15 15), 1.4914 (X10CrMoVNb 11 1), 1.4980 (= A286 = X5 NiCrTi 26 15), RGTX2 KV (X10NiCrMoTiB 25 10) and INCONEL 718 (Ni Cr 19NbMo)
Key words: austenitic steels;cladding;ferritic steels;inconel 718;knk-2 reactor;martensitic steels;mechanical properties;stainless steels;steel-cr15ni15motib;steel-ni26cr15ti2movalb
R&D Category: any or undefined
display the document: 34087387.pdf
KNK II, third core: Safety related investigations (part B) KNK II, dritter Kern: Sicherheitstechnische Untersuchungen (Teil B)
Reetz, AINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.04357.6 - German - 1988
Abstract: The present report describes safety related investigations for the third core of KNK II. The following cases have been considered: reactivity accidents, blockage of a primary pump and simultaneous run-out of the second one, thermal loading of the cooling circuits and local cooling perturbations. The protection targets as they had been defined for the second core, are also reached for the third core. Hereby, a possible drift of the coolant temperatures due to the deposit formation on the fuel pins is admitted to a certain amount. Its tolerable limit is set by the mass flow accident. Since the core configuration, the core surveillance and the process parameters of the circuits of the second and third core are differing only marginally or not at all from each other, the proofs for the stress behavior of the cooling circuits and the damage prevention in case of local cooling perturbations are also almost unchanged. The transitory behavior shows, that the third core is also inherently stable
Key words: coolant loops;flow blockage;knk-2 reactor;loss of flow;reactor accidents;safety analysis
R&D Category: Safety aspects
display the document: 34087394.pdf
Legend and operational data of KNK II/2 (1987) Legende und Betriebsdaten von KNK II/2 (1987)
Alfke, H.-WKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--003 - German - 1988
Abstract: This report describes the KNK II legend for 1987 together with the main technical data and the operational data for the areas fuel, energy production and energy supply, availability and radiation protection. For the better understanding of tables and figures, data of the terminated KNK II first-core operation are also included
Key words: availability;energy supplies;knk-2 reactor;power generation;radiation protection;reactor operation
R&D Category: any or undefined
display the document: 34087478.pdf
Calculation of DND-signals in case of fuel pin failures in KNK II with the computer code FICTION III Berechnung der DND-Signale beim Auftreten von Brennstabdefekten in der KNK II mit dem Rechencode FICTION III
Schmuck, IKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--18.01.06P01B - German - 1990
Abstract: In KNK II two delayed neutron detectors are installed for quick detection of fuel subassembly cladding failures. They record the release of the precursors of the emitters of delayed neutrons into the sodium. The computer code FICTION III calculates the expected delayed neutron signals for certain fuel pin failures, where the user has to set the boundary conditions interactively. In view of FICTION II the advancement of FICTION III consists of the following items: application of the data sets of 105 isotopes, distinction of thermal and fast neutron induced fission, partitioning of the sodium flow into two circuits, consideration of the specific fission rates in 10 fuel pin sections, elaboration of the user's interaction possibilities for input/ output. The capability of FICTION III is shown by means of two applications (UNi-test pin on position 100 and the third KNK fuel subassembly cladding failure). Object of further evaluations will be among other things the analysis of increased delayed neutron signals in regard to the fault location and dimension
Key words: computer program documentation;delayed neutrons;f codes;failed element detection;fuel assemblies;fuel element failure;knk-2 reactor;monitoring;neutron detection;reactor safety
R&D Category: -Failure detection
display the document: 34086372.pdf
KNK II third core, Safety Report KNK II dritter Kern, Sicherheitsbericht
INTERATOM GmbH, Bergisch Gladbach (Germany), Kernforschungszentrum Karlsruhe GmbH (DE), Kernkraftwerk-Betriebsgesellschaft mbH Karlsruhe (DE)IA--75.19200.0 - German - 1990
Abstract: The compact sodium cooled reactor plant KNK is a test reactor with 58 MW thermal and 20 MW electrical power. After being operated until 1974 with a thermal core, the plant has been modified to operate with a fast core using Uranium/Plutonium-oxide fuel. It was operated with the first core until 1983. In June 1983 the second core had been loaded, which had been licensed first for a residence time of 455 equivalent full-power days (efpd) and later for a residence time extension of up to 720 efpd. In order to further pursue the main task of KNK II to serve as test bed for the development, test and design validation of core assemblies for fast sodium cooled reactors, KfK and KBG applied for the license for the loading and operation of a third core with a residence time of 720 efpd. The present safety report as part of the application documents describes the technical details of the reactor core together with the resulting influences of concerned adjoining systems and components. The plant safety systems, accident analysis, the radiation protection, the waste disposal and the continuation of the test program are outlined
Key words: knk-2 reactor;mixed oxide fuels;radiation protection;radioactive waste disposal;reactor cores;reactor licensing;reactor operation;research programs;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087399.pdf
KNK II third core, short description KNK II dritter Kern, Kurzbeschreibung
INTERATOM GmbH, Bergisch Gladbach (Germany), Kernforschungszentrum Karlsruhe GmbH (DE), Kernkraftwerk-Betriebsgesellschaft mbH Karlsruhe (DE)IA--75.19201.2 - German - 1990
Abstract: The compact sodium cooled reactor plant KNK is a test reactor with 58 MW thermal and 20 MW electrical power. After being operated until 1974 with a thermal core, the plant has been modified to operate with a fast core using Uranium/Plutonium-oxide fuel. It was operated with the first core until 1983. In June 1983 the second core had been loaded, which had been licensed first for a residence time of 455 equivalent full-power days (efpd) and later for a residence time extension of up to 720 efpd. In order to further pursue the main task of KNK II to serve as test bed for the development, test and design validation of core assemblies of fast sodium cooled reactors, KfK and KBG applied for the license for the loading and operation of a third core with a residence time of 720 efpd. The present short description as part of the application documents describes the reactor core with the core elements and the continuation of the test program. Subsequently the plant safety systems, the irradiation protection and the waste disposal are outlined
Key words: fuel assemblies;knk-2 reactor;mixed oxide fuels;reactor cores;reactor fueling;reactor licensing;reactor operation;research programs;sodium
R&D Category: any or undefined
display the document: 34087400.pdf
Legend and operational data of KNK II/2 (1988-1990) Legende und Betriebsdaten von KNK II/2 (1988-1990)
Lauber, D.;Richard, HKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--004 - German - 1990
Abstract: This report describes the KNK II legend for the period 1988-1990 and the operational data for the areas fuel, energy production and energy supply, availability and radiation protection. For the better understanding of tables and figures, data of the terminated KNK II first-core operation are also included
Key words: availability;energy supplies;knk-2 reactor;radiation protection;reactor cores;reactor operation
R&D Category: any or undefined
display the document: 34087479.pdf
Residence time extension of KNK II/2: Reloadings and nuclear start-up measurements (F3, F4) Standzeitverlaengerung der KNK II/2: Umladungen und nukleare Inbetriebnahmemessungen (F3, F4)
Boehnel, K.;Richard, HKernkraftwerk-Betriebsgesellschaft mbH (Germany)
KBG--U90/33 - German - 1990
Abstract: The second core of KNK II had been shutdown at the end of its licensed residence time of 455 equivalent full-power days (efpd). After the planned residence time extension up to 720 efpd was licensed, the reloadings were performed which were necessary for the continuation of the operation. The absorbers of the first and of the secondary shut-down system were replaced, and two moderated driver subassemblies were loaded on reflector positions. The present report describes first the reloading and loading processes and subsequently the measurements at zero power and at the power levels of 40, 60, 80 and 100 %. Additionally, a comparison of measured and calculated parameters is presented
Key words: burnup extension;control rod worths;knk-2 reactor;neutron absorbers;reactivity coefficients;reactor operation;reactor shutdown;reactor start-up;scram rods
R&D Category: any or undefined
display the document: 34087734.pdf
Legend and operational data of KNK II/2 (1991) Legende und Betriebsdaten von KNK II/2 (1991)
Lauber, D.;Richard, HKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--005 - German - 1992
Abstract: This report describes the KNK II legend for the year 1991 with the final shutdown on August 23rd and the operational data for the areas fuel, energy production and energy supply, availability and radiation protection. For the better understanding of tables and figures, data of the terminated KNK II first-core operation are also included
Key words: availability;knk-2 reactor;power generation;radiation protection;reactor cores;reactor operation;reactor shutdown
R&D Category: any or undefined
display the document: 34087480.pdf