Component Category: Reactor components
18 documents found
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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 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
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
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
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
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
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
Progress report on research and development in 1981 of Institut fuer Radiochemie. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1981 des Instituts fuer Radiochemie
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer RadiochemieKFK--3299 - German - 1982
Abstract: The project fast breeding reactor (PSB) investigates oxide fuel rods and the system contamination of sodium cooled nuclear reactors. The project reprocessing and waste treatment (PWA) investigates voloxidation as an alternative waste gas purification, laboratory automation and solid and alpha containing wastes. Investigations of fission product liberation at the LWR core melting were done by the project nuclear safety (PNS). Furthermore procedures and components in connexion with nuclear matter supervision were developed. In the field of nuclear data determination air chemistry and the chemistry of the actinoids were investigated. Waste water, water desalting by ion exchange and chemical oxidation in water purification were treated, too. (SPI)
Key words: air pollution;condensed aromatics;coolants;corium;desalination;fission product release;fission products;german fr organizations;knk-2 reactor;performance;primary coolant circuits;radioactive waste processing;radioactive waste storage;radiochemistry;safety;sodium;voloxidation process;water chemistry;zeolites
R&D Category: any or undefined
display the document: 15062364.pdf
Irradiation experiments in the KNK II reactor Bestrahlungsexperimente im KNK II Reaktor
Bojarsky, E.;Haefner, H.E.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.12P08B - German - 1984
Abstract: KNK II is a small sodium cooled experimental power reactor with 20 MW(e). There are only restricted possibilities for in-pile experiments, especially with instrumented devices. Nevertheless, after more than 10 years of successful operation, the reactor is now more and more used for the experimental programme for fast sodium-cooled breeder reactors. A survey is given of different in pile experiments devoted to cladding and other structural materials as well as to fuel pin bundles. Some of them are installed or finished, others are in the design stage for the next core loading
Key words: fuel element clusters;irradiation;knk-2 reactor;materials testing;performance testing
R&D Category: any or undefined
display the document: 34087766.pdf
Influence of the KNK II postscram control on the thermohydraulic plant behavior
Schubert, B. (GKSS-Forschungszentrum Geesthact GmbH, West Germany)CONF-850410--Vol.2 - English - 1985
Abstract: In LMFBRs the balance of generated and removed heat is highly distorted during the period following shortly after scram, because the core flow drops much less than the reactor power does even though the pumps are tripped as fast as possible after scram signal occurs. Due to this sharp temperature gradients are produced in the core and enter the piping system of the plant despite the damping effect of the upper plenum. In order to reduce the temperature variations occurring shortly after scram a flow control system is used in the German loop-type LMFBR. Theoretical investigations are presented to demonstrate how postscram control systems work and can help to limit thermal shocks in the plant. In addition several parameters of the system are investigated to show their influence
Key words: flow rate;fluid flow;heat transfer;knk-2 reactor;pipes;reactor control systems;reactor cooling systems;reactor cores;reactor protection systems;reactor safety;scram;thermal shock
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 17036590.pdf
Irradiation capsules 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 G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4151 - German - 1986
Abstract: A novel irradiation capsule with self-acting temperature control was developed for irradiation of material specimens in material testing elements, not amenable to instrumentation, of the KNK II and SNR 300 reactors. The capsule is equipped with a gas-buffered heat pipe which, acting as a variable heat transfer system, guarantees maintaining of 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, through gamma-heating, are brought to elevated temperatures. 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 6500C was attained with high accuracy. It is planned to irradiate the capsules in the SNR 300 reactor at the same temperature level. (orig.)
Key words: annular space;cylindrical configuration;heat pipes;heat transfer;helium;irradiation capsules;knk-2 reactor;power distribution;reactor cores;rhodium;snr reactor;temperature dependence;thermal conductivity;thermal insulation
R&D Category: Reactor physics
display the document: 18032779.pdf
Controllable irradiation facilities for KNK II. Regelbare Bestrahlungseinrichtungen fuer den KNK II-Reaktor
Schmidt, L.;Lehning, H.;Mueller, K.;Reimann, GKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4149 - German - 1986
Abstract: Material irradiation experiments are being performed at five core positions of the KNK II reactor at the Karlsruhe Nuclear Research Center. Two positions have been provided with penetrations in the reactor lid for measurement and supply lines and, therefore, they are suited to accomodate instrumented test rigs. These are the central core position at which an irradiation channel has been realized with the help of a special carrier fuel element, and the reflector position 511 in the fifth element row. For the central position an irradiation rig has been developed in which eight electrically heated pressure tube specimens can be irradiated simultaneously. The testing conditions such as temperature and internal pressure can be adjusted individually for each specimen in a steady-state or dynamic mode. For the reflector position a test rig is available in which the material specimens are irradiated in electrically heated capsules. Another test rig serves for in-pile testing of switches to be used in a reactor protective system. (orig./GL)
Key words: annular space;electric cables;irradiation devices;irradiation procedures;knk-2 reactor;neutron reflectors;operation;pressure tubes;reactor cores;thermocouples
R&D Category: Reactor physics
display the document: 18042436.pdf
Studies on plant dynamics of sodium-cooled fast breeder reactors - verification of a plant model. Untersuchungen zur Anlagendynamik von natriumgekuehlten Schnellen Brutreaktoren - Verifikation eines Anlagenmodells
Schubert, B. (GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.). Inst. fuer Anlagentechnik)GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.);Technische Univ. Braunschweig (Germany, F.R.). Fakultaet fuer Maschinenbau und Elektrotechnik
GKSS--88/E/18 - German - 1988
Abstract: For the analysis of sodium-cooled FBR safety and dynamics theoretical models are used, which have to be verified. In this report the verification of the plant model SSC-L is conducted by the comparison of calculated data with measurements of the experimental reactors KNK II and RAPSODIE. For this the plant model is extended and adapted. In general only small differences between calculated and measured data are recognized. The results are used to improve and complete the plant model. The extensions of the plant model applicability are used for the calculation of a loss of heat sink transient with reactor scram, considering pipes as passive heat sinks. (orig./HP) With 69 figs., 10 tabs
Key words: after-heat removal;computerized simulation;heat sinks;knk-2 reactor;lmfbr type reactors;mathematical models;rapsodie reactor;reactivity;reactor accidents;reactor kinetics;reactor physics;reactor safety;scram;sodium cooled reactors;transients;verification
R&D Category: Systems analysis
display the document: 19095973.pdf
Results of experiments in the THIBO II test section Ergebnisse aus Experimenten in der THIBO II-Strecke
Bojarsky, E.;Deckers, H.;Lehning, H.;Piel, D.;Reiser, H.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.12P06C - German - 1989
Abstract: It was possible to prove in 1988 in the course of the THIBO I experiments. That under certain operating conditions thermohydraulically induced rod damaging oscillations may occur in sodium cooled Mark II fuel elements. Since May 1989 another THIBO II test series has been performed in a new test section of the sodium loop of the IMF III. The area of the coolant channel was reduced to approximately half its previous surface so that the thermohydraulic conditions come very close to those prevailing in the KNK II reactor. The experiments have shown that even with minor sodium enthalpy raises and low rating, respectively, motions of the fuel pins can be induced. This applies also in cases where the clearance of the pin in the spacer has been set to realistically low values
Key words: coolant loops;enthalpy;fuel pins;knk-2 reactor;mechanical vibrations;oscillations;sodium;thermal hydraulics
R&D Category: -Thermo hydraulic testing
display the document: 34086306.pdf
THIBO-Experiments: Thermohydraulically Induced Fuel Rod Oscillations in Sodium Cooled Reactors
Bojarsky, E.;Deckers, H.;Lehning, H.;Piel, D.;Reiser, H.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--18.04.04P04A - English - 1990
Abstract: The KNK II reactor in Karlsruhe experienced fuel element damages which could not be traced back to hydraulically excited vibrations. Instead, some indications pointed to low-frequency fuel rod oscillations caused by temperature differences over the circumference of the fuel rod as a result of the high specific rod power and the clearance of fuel rods in their spacers. In 1988, specific experiments were started in the sodium loop of the IMF III to investigate this phenomenon (THIBO experiments, THIBO standing for Thermal Induced pin BOwing). The rod movements were made visible and detected in a reproducible way. Since May 1989, another series of tests (THIBO II) have been run in a second test section. In this case, the cooling channel area was reduced so much that the thermal-hydraulic conditions approximated very closely those existing in the KNK II reactor. The experiments have shown that the fuel rods may start moving already at relatively low sodium temperature increases and low partial loads, respectively, even if the rod clearance in the spacer was set to realistically low levels
Key words: bowing;coolant loops;flow stress;fuel pins;fuel rods;knk-2 reactor;mechanical vibrations;oscillations;reactor kinetics;spacers;stress analysis;thermal hydraulics
R&D Category: -Thermo hydraulic testing
display the document: 34086308.pdf
Final Report THIBO-Experiments: Thermal-hydraulically excited fuel pin oscillations in sodium cooled fast reactors Abschlussbericht. THIBO-Experimente: Thermohydraulisch induzierte Brennstaboszillationen in Schnellen Natriumgekuehlten Reaktoren
Bojarsky, E.;Deckers, H.;Lehning, H.;Piel, D.;Reiser, H.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--18.04.04P04B - German - 1990
Abstract: The KNK II reactor in Karlsruhe experienced fuel element damages which could not be traced back to hydraulically excited vibrations. Instead, some indications pointed to low-frequency fuel rod oscillations caused by temperature differences over the circumference of the fuel rod as a result of the high specific rod power and the clearance of fuel rods in their spacers. In 1988, specific experiments were started in the sodium loop of the IMF III to investigate this phenomenon (THIBO experiments, THIBO standing for Thermal Induced pin Bowing). The rod movements were made visible and detected in a reproducible way. In 1989, another series of tests (THIBO II) have been run in a second test section. In this case, the cooling channel area was reduced so much that the thermal-hydraulic conditions approximated very closely those existing in the KNK II reactor. The experiments have shown that the fuel rods may start moving already at relatively low sodium temperature increases and low partial loads, respectively, even if the rod clearance in the spacer was set to realistically low levels
Key words: coolant loops;fuel pins;fuel rods;knk-2 reactor;mechanical vibrations;reactor kinetics;sodium;thermal hydraulics
R&D Category: -Thermo hydraulic testing
display the document: 34086309.pdf
Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK)
Hillebrand, I. (Forschungszentrum Karlsruhe (Germany));Benkert, J. (Westinghouse Reaktor (Germany))IAEA-TM--25332 - English - 2002
Abstract: The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 1. The maximum Co-60 activation is on the order of 107-108 Bq/g. The maximum dose rate in the middle of the vessel was measured in April 1997 to be 55 Sv/h. The difficulty involved especially in dismantling KNK, on the one hand, is posed by the residual sodium in the plant, which determines the choice of neither wet nor thermical techniques to be used in disassembly. Another difficulty is caused by the depth of activation by fast neutrons, as a result of which not only the reactor vessel proper, but also the entire primary shield (60 cm of grey cast iron) and large parts of the biological shield must be disassembled and disposed of under remote control. (author)
Key words: activity levels;biological shields;cast iron;knk-2 reactor;licensing procedures;planning;reactor decommissioning;reactor dismantling;reactor vessels;remote control
R&D Category: Decontamination, decommissioning, disassembly
display the document: 34029242.pdf