R&D Category: Reactor physics
49 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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 06169206.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
Components Category: -Core components
display the document: 34087420.pdf
The carbide fuel element for the reload of the KNK-II. Das Karbid-Brennelement fuer die KNK II-Nachladung
Bojarsky, E. (Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung)KFK--2416 - German - 1976
Abstract: Within the framework of the study on the irradiation behaviour of carbide fuel rods, complete carbide fuel elements are to be tested in the fast neutron flux of the KNK II. The main data and the construction of the carbide fuel elements are presented. Some data of the KNK II carbide elements with regard to thermo-hydraulics are compared with the data of an oxide element of the type Mark II. (HR)
Key words: comparative evaluations;fuel elements;knk-2 reactor;plutonium carbides;pressure drop;specifications;testing;uranium carbides
Components Category: --Fuel assemblies
display the document: 08335294.pdf
Assessment of the design of oxidic fuels and acceptance criteria for fuel elements (KNK 2, KWO). Beurteilung der Auslegungen von oxidischen Brennstoffen und Abnahmekriterien fuer Brennelemente (KNK 2, KWO)
Beisswenger, H.;Brodt, F. (Technischer Ueberwachungs-Verein Baden e.V., Karlsruhe (Germany, F.R.))AED-Conf--78-114 - German - 1978
Abstract: not available
Key words: fuel pellets;inspection;knk-2 reactor;mixtures;obrigheim reactor;performance;plutonium dioxide;quality control;reactor licensing;uranium dioxide
Components Category: --Fuel assemblies
display the document: 09402072.pdf
Concepts of annular fuel elements for installation of irradiation inserts in KNK II and layout of a carbide test bundle Konzepte ringfoermiger Brennelemente zur Aufnahme von Bestrahlungseinsaetzen in KNK II und Entwurf eines Karbidkleinbuendels
Haefner, H.E.;Philipp, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.02P03C - German - 1978
Abstract: A variety of basic proposals for the irradiation of test fuel elements in the test zone of KNK II are being discussed recently. As a further concretization annular fuel elements with two or three rows of oxide fuel pins for the installation of different irradiation devices are considered. In this report the layout of a carbide test bundle in a carrier element with two pin rows is proposed
Key words: annular fuel elements;fuel assemblies;fuel pins;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;specifications
Components Category: --Fuel assemblies
display the document: 34086299.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
Components Category: -Core components
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
Components Category: -Core components
display the document: 34087483.pdf
Design report for core assemblies of KNK II: Driver zone assemblies with moderator Auslegungsbericht fuer Kernelemente KNK II: Treiberzonenelemente mit Moderator
Huesken, J.;Fenneker, K.;Singer, J.;Zihla, W.;Coors, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.01910.8 - German - 1979
Abstract: The report describes the driver zone fuel assemblies with moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;safety standards;specifications;zirconium hydrides
Components Category: --Fuel assemblies
display the document: 34085694.pdf
Design report for core assemblies KNK II/2: Secondary shutdown assemblies Auslegungsbericht fuer Kernelemente KNK II/2: Zweitabschaltelemente
Koenigsdorf, E.;Huesken, J.;Schmitz, K.J.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03541.1 - German - 1979
Abstract: The report describes the secondary shutdown assemblies of the second core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: boron carbides;calculation methods;design;knk-2 reactor;neutron absorbers;reactor shutdown;scram rods
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 34085703.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
Components Category: Reactor components
display the document: 34086290.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
Components Category: -Core components
display the document: 34085695.pdf
Development of an absorber pin with diving bell Entwicklung eines Absorberstabes mit Tauchglocke
Dreyer, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03724.4 - German - 1980
Abstract: The report describes the development of an absorber pin with diving bell (degassed absorber) at INTERATOM since 1974. In comparison with the closed absorber pin, which is presently foreseen for SNR 300, the degassed absorber pin offers the advantage of a longer residence time, since it allows the release of the Helium produced in the boron absorber material and thus avoiding a mechanically straining pressure built-up. During the period from 1974 till 1979 seven major experiments for the test of the diving bell concept had been performed at INTERATOM: five in stagnant sodium, one scram-test in sodium and one bundle test in water. All tests confirmed the operational efficiency of the absorber pin with diving bell. Major affects on the behavior of the concerned materials could not be detected. The development work for the absorber pins with diving bell will be continued with the loading of eight of these pins in KNK II/2 in 1981
Key words: boron carbides;boron;degassing;fuel elements;interstitial helium generation;knk-2 reactor;neutron absorbers;performance testing;research programs;snr reactor
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 34085701.pdf
KNK II, MTE II design report, temperature distribution KNK II, MTE II-Auslegungsbericht, Temperaturverteilung
Puetz, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--33.02637.0 - German - 1980
Abstract: The present report deals with the calculation of the temperature distribution in the Material-Test-Element (MTE II) for KNK II/2. The calculational method includes the influences of the bypasses between the assemblies and the neighbouring assemblies. In the chosen reference case (MTE II mass-flow 0.1 kg/s, bypass mass-flow 0.185 kg/s) a temperature rise of 70 K is reached. The power of the MTE II is 24.8 kW
Key words: calculation methods;design;fuel elements;knk-2 reactor;temperature distribution;thermal hydraulics
Components Category: -Core components
display the document: 34085696.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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 34087776.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
Components Category: -Core components
display the document: 34085697.pdf
Design report for core assemblies of KNK II/2: Mark II assemblies of the test zone (Central position)2.4 and 2.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Elemente der Testzone (Zentralelemente) 2.4 und 2.5
Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02749.5 - German - 1981
Abstract: The report describes the Mark II assemblies for the central position of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
Components Category: --Fuel assemblies
display the document: 34085698.pdf
Design report for core assemblies of KNK II/2: Driver zone assemblies without moderator Auslegungsbericht fuer Kernelemente KNK II/2: Treiberzonenelemente ohne Moderator
Bestenreiner, G.;Fenneker, K.;Ricken, E.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02750.2 - German - 1981
Abstract: The report describes the driver zone fuel assemblies without moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: burnup;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
Components Category: --Fuel assemblies
display the document: 34085699.pdf
Design report for core assemblies of KNK II/2: Mark II test zone fuel assemblies on the first ring 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 and 3.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Kranzelemente der Testzone 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 und 3.5
Bestenreiner, G.;Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04164.+ - German - 1981
Abstract: The report describes the Mark II test zone fuel assemblies of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
Key words: calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;reactor cores;safety standards
Components Category: --Fuel assemblies
display the document: 34085702.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
Components Category: -Core components
display the document: 34087481.pdf
KNK - annular fuel element with carbide test bundle: Estimation of the sodium outlet temperature in case of obstruction of the test bundle, respectively the annular carrier element KNK - Ringelement mit 19-Stab Karbid-Testbuendel: Abschaetzung der Natriumaustrittstemperatur bei Verstopfung von Testbuendel bzw. Ringelement
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P62B - German - 1981
Abstract: For KNK II an annular carrier element with an integrated 19-pin carbide test bundle is planned to be placed on a ring position of the test zone. With regard to safety aspects, the effects of obstruction in, both, the annular element and the test bundle on the sodium outlet temperature were studied. It was found that a 60 % reduction of mass flow in the test bundle leads to a temperature increase behind the mixing device of 26 K. This value has been suggested as a limit for reactor scram in order to obviate the possibility of sodium boiling in the test bundle. For the annular element the same value already leads to reactor scram at 16 % mass flow reduction
Key words: annular fuel elements;flow blockage;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;temperature distribution;thermal hydraulics
Components Category: --Fuel assemblies
display the document: 34087758.pdf
Design report for core assemblies KNK II/2: Fuel pins with high density fuel Auslegungsbericht fuer Kernelemente KNK II/2: Brennstaebe mit hoher Dichte
Fenneker, KINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04214.9 - German - 1982
Abstract: The design report describes the mechanical and thermal behavior of fuel pins with higher fuel density (94 - 95.5 %) in the second core of KNK II with a residence time of 455 equivalent full-power days. The pins will be loaded into the central position and one position on the first assembly ring. The tasks and the design of the fuel pins are described, and the criteria, methods and results for the design of fuel pins with high density are presented. The admissibility of the loadings for cladding and fuel, to be expected during the operation in KNK II/2, is demonstrated
Key words: burnup extension;calculation methods;cladding;density;design;fuel assemblies;fuel pellets;fuel pins;knk-2 reactor
Components Category: --Fuel pins
display the document: 34085704.pdf
Fast breeder physics and nuclear core design. Schnellbrueterphysik und nukleare Kernauslegung
Marth, W.;Schroeder, R. (eds.)Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3543 - German - 1983
Abstract: This report gathers the papers that have been presented on January 18/19, 1983 at a seminar ''Fast breeder physics and nuclear core design'' held at KfK. These papers cover the results obtained within about the last five years in the r+d program and give some indication, what still has to be done. To begin with, the ''tools'' of the core designer, i.e. nuclear data and neutronics codes are covered in a comprehensive way, the seminar emphasized the applications, however. First of all the accuracies obtained for the most important parameters are presented for the design of homogeneous and heterogeneous cores of about 1000 MWe, they are based on the results of critical experiments. This is followed by a survey on activities related to the KNK II reactor, i.e. calculations concerning a modification of the core as well as critical experiments done with respect to re-loads. Finally, work concerning reactivity worths of accident configurations is presented: the generation of reactivity worths for the input of safety-related calculations of a SNR 2 design, and critical experiments to investigate the requirements for the codes to be used for these calculations. These papers are accompanied by two contributions from the industrial partners. The first one deals with the requirements to nuclear design methods as seen by the reactor designer and then shows what has been achieved. The latter one presents state, trends, and methods of the SNR 2 design. The concluding remarks compare the state of the art reached within DeBeNe with international achievements. (orig.)
Key words: computerized simulation;control rod worths;fbr type reactors;knk-2 reactor;planning;reactivity coefficients;reactor cores;reactor physics;reactor safety experiments;reactor safety;research programs
Components Category: any or undefined
display the document: 15028461.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
Components Category: -Core components
display the document: 15028466.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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 16061281.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
Components Category: -Core components
display the document: 34085707.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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 34085708.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
Components Category: -Core components
display the document: 34085709.pdf
Fast breeder fuel pin bundle tests in the KNK II-reactor
Haefner, H.E.;Bojarsky, EKernforschungszentrum 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--4141 - English - 1986
Abstract: Three variants of ring elements with test bundles will be reported in this paper: In a first step a ring element was built with a permanently integrated test bundle (19 carbide pins of the Karlsruhe reference concept) while the proven fuel element components have been largely maintained. This irradiation will be completed in autumn 1986 after 380 full power days of operation. The central topic of this paper will be the technique of reloadable ring elements with replaceable test bundles. A first experiment, TOAST, is in preparation. For this experiment, above all the components of the fuel element head and foot had to be newly developed and tested. A special version of double-walled replaceable test bundles to be used in the TETRA temperature transient experiments will be briefly mentioned. It is envisaged in these experiments to vary in a defined manner the coolant flow at remotely assembled test bundles consisting of 19 KNK pins each having undergone a high burnup and to use a measuring and control plug placed on the test bundle so that a variety of fuel pin temperature programs can be realized. Finally, some additional aspects of bundle design will be indicated. (orig./GL)
Key words: flow rate;fuel element clusters;knk-2 reactor;loss of flow;reactor channels;reactor cores;simulation;temperature dependence;temperature distribution;testing;transients
Components Category: --Fuel assemblies
display the document: 18028687.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
Components Category: Reactor components
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
Components Category: Reactor components
display the document: 18042436.pdf
Fuel assembly NY-308 Compilation of the fuel and fuel pin fabrication data from the T264 data bank system BESEX Das KNK II/2 Brennelement NY-308 Zusammenstellung der Brennstoff- und Brennstabfertigungs-Daten aus dem T264-Datenbanksystem BESEX
Patzer, GINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06863.8 - German - 1986
Abstract: The fuel assembly NY-308 will be the first assembly of the second core of KNK II to undergo post-irradiation examinations. It had reached a residence time of 273.5 equivalent full-power days. For the planning of the post-irradiation examinations and as support for a valuation of their results, the data of the fuel and fuel pin fabrication are presented in this report on the basis of the data bank system BESEX. The presentation is given in form of assembly cross-sections and in different tables, which are compiled according to different view points
Key words: burnup;data compilation;fissile materials;fuel assemblies;fuel pins;knk-2 reactor;post-irradiation examination
Components Category: --Fuel pins
display the document: 34085712.pdf
KNK II: Evaluation of the neutron dosimetry MTE1 on position 517 KNK II: Auswertung der Neutronendosimetrie MTE1 auf Position 517
Timm, WINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06953.1 - German - 1986
Abstract: The present report documents the calculational evaluation of the measured activation rates of Fe/Ti-foils and the measured axial and radial distribution of the activity within the Co-probe in the Material Test Element MTE 1 on position 517 of KNK II after irradiation in the first core and in the second core until 517 equivalent full-power days. The evaluation of the different activated isotopes (Co60, Sc46, Mn54) gives consistent results. The values agree well with the results of the design calculations. The axial distribution of the Co-activation also shows very good agreement with the theoretical results. All together, the present evaluation of the neutron dosimetry is a valuable confirmation of the design methods
Key words: activation analysis;cobalt 60;evaluation;fuel cycle;knk-2 reactor;manganese 54;neutron dosimetry;neutron flux;scandium 46;spatial distribution
Components Category: -Monitoring systems, their circuits and electronics
display the document: 34085715.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
Components Category: -Core components
display the document: 34085716.pdf
KNK II, third core: Design report for Mark II test zone NY401 to NY406 fuel assemblies on the first ring KNK II, dritter Kern: Auslegungsbericht fuer Mark II Kranzelemente der Testzone NY401 bis NY406
Ricken, E.;Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07020.4 - German - 1986
Abstract: The report describes the Mark II fuel assemblies of the first test zone ring 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: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor
Components Category: --Fuel assemblies
display the document: 34085717.pdf
KNK II, third core: Design report for driver zone assemblies NU 401 bis 407 (without moderator) and NW 401 bis 421 (with moderator) KNK II, dritter Kern: Auslegungsbericht fuer Treiberzonenelemente NU 401 bis 407 (ohne Moderator) und NW 401 bis 421 (mit Moderator)
Ricken, E.;Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07025.3 - German - 1986
Abstract: The report describes the assemblies of the driver zones without and with moderator 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: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;moderators;safety standards;zirconium hydrides
Components Category: --Fuel assemblies
display the document: 34085720.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
Components Category: -Core components
display the document: 34087390.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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
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
Components Category: -Protective and shut-down systems (shutdown rods and drive mechanisms, passive control systems, support systems)
display the document: 34085719.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
Components Category: -Core components
display the document: 34087392.pdf
The KNK II/1 fuel assembly NY-205: Compilation of the irradiation history and the fuel and fuel pin fabrication data of the INTERATOM data bank system BESEX Das KNK II/1 Brennelement NY-205: Zusammenstellung des Bestrahlungsverlaufs sowie der Brennstoff- und Brennstabfertigungsdaten aus dem INTERATOM Datenbanksystem BESEX
Patzer, G.;Geier, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07463.3 - German - 1988
Abstract: The fuel assembly NY-205 has been irradiated during the first and the second core of KNK II with a total residence time of 832 equivalent full-power days. A maximum burnup of 175.000 MWd/tHM or 18.6 % was reached with a maximum steel damage of 66 dpa-NRT. For the cladding the materials 1.4970 and 1.4981 have been used in different metallurgical conditions, and for the Uranium/Plutonium mixed- oxide fuel the most important variants of the major fabrication parameters had been realized. The assembly will be brought to the Hot Cells of the KfK Karlsruhe for post-irradiation examination in February 1988, so that the knowledge of the fabrication data is of interest for the selection of fuel pins and for the evaluation of the examination results. Therefore this report compiles the fuel and fuel pin fabrication data from the INTERATOM data bank system BESEX and additionally, an overview of the irradiation history of the assembly is given
Key words: burnup extension;cladding;data compilation;fuel assemblies;hot cells;knk-2 reactor;mixed oxide fuels;physical radiation effects;reactor cores;steels
Components Category: --Fuel assemblies
display the document: 34085729.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
Components Category: -Core components
display the document: 34087380.pdf
KNK II, third core: Design Report of the Mark-II subassemblies of the test zone N-401 to NY-406 and NZ-401 KNK II, dritter Kern: Auslegungsbericht fuer Mark-II Elemente der Testzone N-401 bis NY-406 und NZ-401
Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07555.0 - German - 1988
Abstract: The report describes the Mark-II subassemblies of the test zone of the KNK II third core. The design of the subassemblies is justified together with their single components: fuel pin, pin bundle, duct, head, foot and grid-plate insert. Criteria, design methods and design results of the subassemblies and the components are described, and the respectation of the design targets is proved for the foreseen residence time of 720 equivalent full-power days
Key words: calculation methods;design;ducts;fuel elements;fuel pins;knk-2 reactor
Components Category: --Fuel assemblies
display the document: 34087381.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
Components Category: -Core components
display the document: 34087382.pdf
KNK II, third core: Design Report of the breeder assemblies NR-230R, NR-231R, NR-233D and NR-234D KNK II, dritter Kern: Auslegungsbericht fuer die Brutelemente NR-230R, NR-231R, NR-233D und NR-234D
Ricken, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07630.1 - German - 1988
Abstract: The report describes the blanket assemblies of the third core of KNK II and their operational behavior. The assemblies and their individual components are described and the design criteria, design methods and design results are presented. With the help of enveloping proofs the respectation of the design targets up to the foreseen residence time of 720 equivalent full-power days is evidenced
Key words: breeding blankets;calculation methods;design;fuel assemblies;knk-2 reactor;reactor cores
Components Category: --Fuel assemblies
display the document: 34087384.pdf
Continuous post-scram control for KNK II Unterbrechungsfreie Nachscramregelung fuer KNK II
Niebel, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.04243.8 - German - 1988
Abstract: On suggestion of the operating utility the present report discusses the feasibility and the expected advantages of a modification of the post-scram control and regulation system of KNK II. In the present procedure several different process controlled phases are passed after each scram, whereas in the alternative concept a continuously working post-scram control is proposed, very similar to the SNR 300 concept. In this concept the coolant flow rates are adapted to the actual situation of the core, such as loading, power history and burnup, thus avoiding the disadvantages of a flow rate control without feedback, as applied in the present KNK II concept. The modification of the post-scram control has to be designed and verified by a series of dynamic analysis, and in parallel to that the electrotechnical planning and realization can be done
Key words: flow rate;fluid flow;knk-2 reactor;reactor control systems;reactor safety;scram
Components Category: -Monitoring systems, their circuits and electronics
display the document: 34087393.pdf
KNK II third core: design report for the annular fuel elements on the central position to accommodate material test inserts NZ 402 and NZ 403 KNK II 3. Kern: Auslegungsbericht fuer die Ringbrennelemente auf der Zentralposition zur Aufnahme von Materialtesteinsaetzen NZ 402 und NZ 403
Schmidt, L.;Mueller, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.12P06A - German - 1989
Abstract: Since August 1984 irradiation experiments with temperature controlled pressure tube probes are being performed in the central position of KNK II. This is part of a long-term experimental program for the development of irradiation resistant reactor materials, which shall also be continued in the third core. The necessary irradiation channel is provided by a special annular fuel element. The present report describes the annular fuel elements for the third core. Aspects of the subassembly design are considered on the basis of the annular element design for the second core and the standard elements of the third core. Two annular elements NZ 402 and NZ 403 (as reserve) are available. It is demonstrated that the expected loadings will allow an unperturbed operation of the annular elements on the central position of the third core
Key words: annular fuel elements;knk-2 reactor;materials testing;reactor cores;reactor materials
Components Category: --Fuel assemblies
display the document: 34086304.pdf
Progress in the Development of the Consulting Core Surveillance System COCOSS for KNK Weiterentwicklung des Consulting Core Surveillance System COCOSS an der KNK
Hoffmann, GKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--18.01.06P01A - German - 1990
Abstract: A very flexible data collecting and evaluation system is necessary to develop and test methods for detection and localization of fuel subassembly cladding failures in LMFBR's and to make predictions on their further development. For this purpose a new version of COCOSS (Consulting Core Surveillance System) has been developed and installed at KNK II. The new features of COCOSS are described in this report. The measuring system consists of two components, a data acquisition system in the experimenter room of the KNK II and a data evaluation computer in the IRE. The data acquisition computer at the KNK II is connected via a modem line to the evaluation computer. Several I/O-devices for monitoring the evaluation computer and for output of measuring results are connected from the KNK II to IRE with further modem lines. An 'emergency program' for evaluating the measured data is started automatically at the acquisition computer if the data line or the computer at the IRE is not available. By this way continuous data acquisition and evaluation is assured
Key words: computerized control systems;data acquisition systems;evaluated data;failed element detection;fuel element failure;knk-2 reactor;reactor control systems;reactor safety
Components Category: -Monitoring systems, their circuits and electronics
display the document: 34086371.pdf
THIBO experiments. Experiments on thermohydraulically induced fuel rod oscillations in a sodium flow. Final report
Bojarsky, E.;Deckers, H.;Lehning, H.;Piel, D.;Reiser, H.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Materialforschung;Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung
KFK--4798 - English - 1991
Abstract: The KNK II in Karlsruhe experienced fuel element damage 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). 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 thermohydraulic conditions very closely approximate those existing in the KNK II reactor. The experiments have shown that fuel rods may start moving already at relatively low sodium temperature increase and low partial loads, respectively, even if the rod clearance in the spacer was set to realistically low levels. (orig.)
Key words: cracks;flow rate;fuel rods;hydraulics;image scanners;in pile loops;knk-2 reactor;mass transfer;oscillations;sodium;spacers;temperature distribution;thermocouples;thermodynamics
Components Category: --Fuel pins
display the document: 23002234.pdf