Component Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
17 documents found
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Diverse shutdown systems for the KNK-1, KNK-2, and SNR-300 reactors
Morgenstern, F.H.;Buchholz, H.;Krueger, H.;Roehrs, H. (INTERATOM, Bensberg, Ger.)CONF-740401--P3 - English - 1974
Abstract: not available
Key words: knk reactor;knk-2 reactor;performance;reactor protection systems;reactor shutdown;snr reactor;specifications
R&D Category: Reactor physics
display the document: 06169206.pdf
Design report for core assemblies KNK II/2: Secondary shutdown assemblies Auslegungsbericht fuer Kernelemente KNK II/2: Zweitabschaltelemente
Koenigsdorf, E.;Huesken, J.;Schmitz, K.J.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03541.1 - German - 1979
Abstract: The report describes the secondary shutdown assemblies of the second core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;calculation methods;design;knk-2 reactor;neutron absorbers;reactor shutdown;scram rods
R&D Category: Reactor physics
display the document: 34085700.pdf
Design report for core assemblies KNK II/2: Standard control assemblies and control assemblies with test pins Auslegungsbericht fuer Kernelemente KNK II/2: Standard-Regeltrimmelemente und Regeltrimmelemente mit Versuchsstaeben
Ricken, E.;Schmitz, K.J.;West, G.;Sperber, F.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04177.9 - German - 1979
Abstract: The report describes the control assemblies of the second core of KNK II and their operational behavior during the foreseen residence time of 455 equivalent full-power days. There are three standard assemblies with closed pins with B4C pellets, one assembly with 49 pins filled with B4C pellets and three pins each filled with Eu2O3 and EuB6 pellets and one assembly, in which degassed pins with diving bell or porous plug, respectively, will be tested. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;burnable poisons;burnup extension;calculation methods;control elements;europium borides;europium oxides;fuel cycle;knk-2 reactor;neutron absorbers;reactor cores;reactor safety;scram rods
R&D Category: Reactor physics
display the document: 34085703.pdf
Investigation of different reactor protection systems Untersuchung verschiedener Reaktorschutzsysteme
Eggenberger, O.;Gmeiner, L.;Nehmer, J.;Racke, W.;Voges, UKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--01.02.19P23A - German - 1979
Abstract: It is the goal of this report to evaluate and to compare the computerized reactor protection systems of different existing plants and to develop a methodology for application in fast reactors and to be tested in KNK II. Within the 14 plants under investigation four are fast reactors and the others are thermal reactors
Key words: computerized control systems;fast reactors;knk-2 reactor;performance testing;reactor protection systems;thermal reactors
R&D Category: Safety aspects
display the document: 34086370.pdf
Development of an absorber pin with diving bell Entwicklung eines Absorberstabes mit Tauchglocke
Dreyer, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03724.4 - German - 1980
Abstract: The report describes the development of an absorber pin with diving bell (degassed absorber) at INTERATOM since 1974. In comparison with the closed absorber pin, which is presently foreseen for SNR 300, the degassed absorber pin offers the advantage of a longer residence time, since it allows the release of the Helium produced in the boron absorber material and thus avoiding a mechanically straining pressure built-up. During the period from 1974 till 1979 seven major experiments for the test of the diving bell concept had been performed at INTERATOM: five in stagnant sodium, one scram-test in sodium and one bundle test in water. All tests confirmed the operational efficiency of the absorber pin with diving bell. Major affects on the behavior of the concerned materials could not be detected. The development work for the absorber pins with diving bell will be continued with the loading of eight of these pins in KNK II/2 in 1981
Key words: boron carbides;boron;degassing;fuel elements;interstitial helium generation;knk-2 reactor;neutron absorbers;performance testing;research programs;snr reactor
R&D Category: Reactor physics
display the document: 34085701.pdf
Comparison of diffusion- and transportcode-results in the course of the evaluations of the SNEAK 11B1 control rod experiments Vergleich von Diffusions- und Transportcode-Ergebnissen bei der Auswertung von Kontrollstabexperimenten im Rahmen des SNEAK 11B1-Experimentierprogramms
Henneges, G.;Kuefner, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P43B - German - 1980
Abstract: SNEAK 11B1 was the simulation of the first reload core of KNK II. Extensive subcritical control rod worth experiments were performed in this assembly. The evaluation of these experiments with diffusion codes revealed ratios between calculated and measured values in the range of 1.03 to 1.21. To clarify this large spread, transport calculations and parametric studies were performed. In this report the results of SN-calculations are described and compared with diffusion results, and discrepancies are pointed out. The determination of the neutron flux level at the detector position is not possible with SN-codes since ray-effects are preventing meaningful evaluations. The comparison of diffusion- and transport-results is also showing considerable discrepancies
Key words: calculation methods;control rod worths;discrete ordinate method;knk-2 reactor;neutron diffusion equation;neutron flux;sneak reactor;subcritical assemblies;zero power reactors
R&D Category: Reactor physics
display the document: 34087776.pdf
Analysis of reactivity noise measured at KNK II with respect to vibrations of control rods and primary loop components
Mitzel, F.;Ansary, S.;Vaeth, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.))INIS-mf--8131 - English - 1981
Abstract: not available
Key words: control elements;knk-2 reactor;mechanical vibrations;primary coolant circuits;reactivity insertions;reactor noise
R&D Category: Safety aspects
display the document: 14755895.pdf
In pile operation and post-examination of degassed and wet B4C absorber pins in the KNK II second core, experimental boundary conditions and documentation of the pre-examination results In-Pile Einsatz und Nachuntersuchung entgaster und nasser B4C-Absorberstaebe im KNK II Folgecore, Experimentelle Randbedingungen und Dokumentation der Voruntersuchungsergebnisse
Hoeller, P.;Hoerle, MINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--54.05968.* - German - 1983
Abstract: In the frame of the KNK II test program twenty (out of the total of fifty-five pins) special pins filled with B4C will be irradiated in the control rod NS-305 on position 312 of the KNK II second core. Out of these twenty pins eight pins are equipped with a diving bell, ten are wet pins with porous plugs and two closed pins have the standard design. In the present report this irradiation experiment is justified and the experimental boundary conditions (irradiation data, specifications and pin distribution) are given. The documentation of the pre-irradiation examinations of the B4C pellets and B4C absorber columns (dimensions, masses, densities) is given in tabulated form. The post-irradiation examinations are planned to be performed in the Hot Cells of the KfK Karlsruhe. The final documentation will be provided by INTERATOM
Key words: boron carbides;control elements;irradiation;knk-2 reactor;neutron absorbers;performance;post-irradiation examination;reactor cores;research programs
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087414.pdf
Review of LMFBR absorber development in DeBeNe
Duenner, P.;Steinmetz, B. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--48 - English - 1984
Abstract: The control rods design methods for LMFBRs, design criteria and choice of absorber materials are reviewed in presented paper. The results of the absorber rods material testing and its in-pile behaviour investigation as well as the programme of the future R and D work are also given
Key words: boron 10;boron carbides;helium generation;knk-2 reactor;lmfbr type reactors;materials testing;neutron absorbers;post-irradiation examination;reactor control systems;regulating rods;research programs;snr reactor;specifications;swelling
R&D Category: Reactor physics
display the document: 16061281.pdf
Design report for the test control rod with special pins Auslegungsbericht fuer das Test-Regeltrimmelement mit Sonderstaeben
Willinger, OINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06696.* - German - 1985
Abstract: The report describes the test control rod and its performance during the foreseen operating period of 720 equivalent full-power days. The operation starts with the residence time extension of the KNK II second core. The assembly contains a bundle of 19 pins, containing pellets of different absorber variants for irradiation and in pile testing. These are: Boron carbides from different manufacturers with sodium- or helium-bonding, boron carbides with different material parameters, EuB6 with different fabrication procedures, zirconium hydride as moderator, B4C from the KNK II first core for further irradiation, B4C with shroud, claddings with inner niobium coating. The report describes the methods, criteria and results of the design of the assembly and its components. With the help of generally valid standards for strength criteria the capacitance of the assembly and its components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;coatings;control elements;design;europium borides;fuel assemblies;knk-2 reactor;neutron absorbers;niobium;reactor cores;testing;zirconium hydrides
R&D Category: Reactor physics
display the document: 34085708.pdf
Results of post-irradiation examinations of the absorber NS 201 (with pellets) of the KNK II first core Ergebnisse von Nachbestrahlungsuntersuchungen am Absorber NS 201 der Erstbeladung KNK II/1 (mit pelletierten Absorberstaeben)
Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06852.2 - German - 1986
Abstract: The absorber NS-201 of the KNK II first core has been unloaded after a residence time of 273 equivalent full-power days, because gap closure between pellet and cladding had to be expected in 24 pins with B4C-pellets. Selected pins of this element underwent post-irradiation examinations in the hot cells of the KfK Karlsruhe. The evaluated and interpreted results of the investigations, which are documented in this report, allow the conclusion that the absorber could have been irradiated for the full core residence time. The good irradiation behaviour of the pellets and the cladding without any visible interaction, lead to the plan for further irradiation of a complete pellet column of one pin in the third core of KNK II
Key words: absorber pellets;boron carbides;burnup;destructive testing;knk-2 reactor;neutron absorbers;post-irradiation examination;reactor operation
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085710.pdf
KNK II, third core: Design report for control assemblies KNK II, dritter Kern: Auslegungsbericht fuer Regeltrimmelemente
Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07021.6 - German - 1987
Abstract: The report describes the control assemblies of the third core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of enveloping proofs the respectation of the design targets and criteria is evidenced for the foreseen residence time of 720 equivalent full-power days
Key words: boron carbides;calculation methods;design;knk-2 reactor;neutron absorbers;reactor safety;reactor shutdown;scram rods;standards
R&D Category: Reactor physics
display the document: 34085718.pdf
KNK II, third core: Design report for secondary shutdown assemblies KNK II, dritter Kern: Auslegungsbericht fuer Zweitabschaltelemente
Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07022.8 - German - 1987
Abstract: The report describes the secondary shutdown assemblies of the third core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of enveloping proofs the respectation of the design targets and criteria is evidenced for the foreseen residence time of 720 equivalent full-power days
Key words: boron carbides;burnup extension;calculation methods;design;knk-2 reactor;neutron absorbers;reactor shutdown;scram rods;specifications
R&D Category: Reactor physics
display the document: 34085719.pdf
Irradiation examinations on the KNK II/1 control rod NS-204 Bestrahlungsuntersuchungen am KNK II/1 Absorber NS-204
Geier, FINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.07114.5 - German - 1987
Abstract: The control rod NS-204 has been operating during the whole operating period of the KNK II first core of 400 equivalent full-power days. The assembly contained 55 pins with 93 % enriched granulated B4C. The goal of the post-irradiation examination in the Hot Cells of the KfK Karlsruhe was to get information about the pin performance under irradiation in the fast neutron flux. Main parameters of interest were the helium release rate, the swelling and sintering process of the granulated B4C and the compatibility of the B4C and the cladding material. The report describes the results of the destructive and non-destructive analysis in the Hot Cells. All absorber pins were found to be intact, and maximum B10-burnups of 6.6x10''2''1 captures per cm3 were reached. The helium release rate amounted to maximum 2.5 %
Key words: absorber pellets;boron 10;boron carbides;burnup;cladding;control elements;destructive testing;fuel assemblies;hot cells;knk-2 reactor;nondestructive analysis;performance testing;post-irradiation examination;reactor control systems
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085721.pdf
Investigations of mobility problems of the secondary shutdown unit of KNK Untersuchungen zu den Schwergaengigkeiten der 2. Abschalteinrichtung an der KNK II
Brockmann, K.;Reuter, B.;Schnetgoeke, G.;Zimmermann, EKernkraftwerk-Betriebsgesellschaft mbH (Germany)
KBG--BL89/13.1 - German - 1989
Abstract: During the operation of the second core of KNK II the absorber rods of both shutdown systems showed repeatedly mobility problems, which also caused obligatory reported events. Therefore special investigations were initiated to clarify the reason for these problems, which are described in the present report for the secondary shutdown rods. It was found out that deposits of sodium and its reaction products on the inner surface of the guide tube and on the shielding piston were the origin of the mobility problems due to enlarged friction. Measures to remove these problems are described in the report
Key words: control rod drives;deposition;friction;knk-2 reactor;neutron absorbers;reactor operation;reactor shutdown;scram rods
R&D Category: Safety aspects
display the document: 34087732.pdf
Investigations of mobility problems of the primary shutdown unit of KNK II Untersuchungen zu den Schwergaengigkeiten der 1. Abschalteinrichtung an der KNK II
Brockmann, K.;Reuter, B.;Schnetgoeke, G.;Zimmermann, EKernkraftwerk-Betriebsgesellschaft mbH (Germany)
KBG--BL89/14.1 - German - 1989
Abstract: During the operation of the second core of KNK II the absorber rods of both shutdown systems showed repeatedly mobility problems, which also caused obligatory reported events. Therefore special investigations were initiated to clarify the reason for these problems, which are described in the present report for the primary shutdown rods. It was found out that deposits of sodium and its reaction products on the inner surface of the guide tube and on the shielding piston were the origin of the mobility problems due to enlarged friction. Measures to remove these problems are described in the report
Key words: control rod drives;friction;guide tubes;knk-2 reactor;reactor operation;scram rods;sodium
R&D Category: Safety aspects
display the document: 34087733.pdf
Mobility problems at the KNK II shut-down systems, cause investigations and valuation in comparison with the experience at other plants Schwergaengigkeit an den KNK II- Abschalteinrichtungen, Untersuchungen der Ursachen und Bewertung im Vergleich mit den Erfahrungen anderer Anlagen
Hess, BSiemens AG, Bereich Energieerzeugung, KWU (Germany)
KWU-BGL-N--22-92-007 - German - 1992
Abstract: During the operation of the second core of the fast test reactor KNK II the shutdown systems showed repeatedly problems with their mobility, which also caused to be reported events. The present report gives a summary description of the events in chronological order. The investigations to remove the mobility problems and the resulting design modifications are described together with the comments of the licensing authorities on the way to the restart of the plant. The results of the post-irradiation investigations in the hot cells and of sodium-chemical investigations are also described. In addition to the comparison of the events at the KNK plant itself and a review of the experiences at comparable plants it will be shown that all known cases of mobility problems did only influence the availability of the plant but that the safe shut-down of the plant was never at risk
Key words: control elements;control rod drives;friction;knk-2 reactor;reactor control systems;reactor licensing;reactor operation;reactor start-up
R&D Category: Safety aspects
display the document: 34086312.pdf