R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
7 documents found
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SNEAK-4, a series of physics experiments for KNK II
Engelmann, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK--1022 - English - 1969
Abstract: At the end of 1968 a three months program of neutron physics experiments was performed at SNEAK for the investigation of some nuclear properties of the KNK II reactor. The experiments were conducted by the Karlsruhe Nuclear Research Center in close cooperation with INTERATOM. The results of the measurements on SNEAK assemblies 4A and 4B are reported and compared with calculations. The experimental results of critical mass and reactivities, control rod worths, Doppler coefficient and power distribution were used to draw conclusions for the KNK II design
Key words: comparative evaluations;control rod worths;critical mass;doppler effect;experimental data;fuel assemblies;knk-2 reactor;power distribution;reactivity coefficients;reactor physics;sneak reactor;theoretical data
Components Category: -Core components
display the document: 34087738.pdf
Axial fission rate distribution in SNEAK 11A Axiale Spaltratenverteilung in SNEAK 11A
Moellendorff, U. von;Henneges, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02E - German - 1978
Abstract: In SNEAK 11A -the simulation of a possible reload core of KNK II- axial fission rate distributions of U235, U238 and Pu239 were measured with two independent methods. They are compared with results of r-z-diffusion calculations. For the unexpectedly strong axial asymmetry of the distributions of U235 and Pu239 a qualitative explanation is given
Key words: fission;knk-2 reactor;neutron diffusion equation;nuclear reaction kinetics;plutonium 239;reactor cores;reactor fueling;reactor kinetics;sneak reactor;spatial distribution;two-dimensional calculations;uranium 235;uranium 238;zero power reactors
Components Category: -Core components
display the document: 34087773.pdf
Subcritical experiments in SNEAK 11B1 Unterkritische Experimente in SNEAK 11B1
Henneges, G.;Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02F - German - 1979
Abstract: SNEAK 11B1 was the simulation of the first reload of KNK II with four Mark-I and three Mark-II fuel elements in the test-zone. In the critical state the simulated absorber rods were withdrawn till core upper plane. The reactivity worths of these rods in different insertion configurations were determined with two different subcritical measurement techniques. Values of up to -28 dollar were measured. The present report presents all measured values, calculated results and the correction calculations for the source multiplication measurements. The results are discussed, especially with respect to the suitable detector positions
Key words: comparative evaluations;control elements;control rod worths;experimental data;fuel elements;knk-2 reactor;neutron absorbers;reactivity insertions;sneak reactor;subcritical assemblies;theoretical data;zero power reactors
Components Category: -Core components
display the document: 34087774.pdf
SNEAK-11: Mockup critical studies of a small sodium-cooled fast reactor SNEAK-11: Mockup-Untersuchungen fuer einen kleinen natriumgekuehlten Reaktor
Moellendorff, U. von;Helm, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P42B - German - 1980
Abstract: A series of mockup assemblies for the KNK II fast test reactor was studied in the SNEAK facility. The principal purpose was to furnish to the power reactor designers experimental data for these small, complex and asymmetric assemblies. However, it is also interesting to test the potential of different calculational methods in dealing with certain features of the assemblies. The paper presents some results on fission-rate distributions, sodium-void worth and control-rod worth
Key words: calculation methods;control rod worths;design;experimental data;knk-2 reactor;nuclear reaction kinetics;sneak reactor;sodium;spatial distribution;void coefficient;zero power reactors
Components Category: -Core components
display the document: 34087775.pdf
Measurement of the fission rate distribution in SNEAK 11B2 Messung der Spaltratenverteilung in SNEAK 11B2
Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P62A - German - 1981
Abstract: The report describes the fission rate measurements performed in SNEAK 11B2, which is the simulation of the fresh first reload core of KNK II. It contains all measured values. Comparisons with calculated values have already partly been reported previously
Key words: experimental data;knk-2 reactor;reactor cores;reactor fueling;sneak reactor;zero power reactors
Components Category: -Core components
display the document: 34087777.pdf
SNEAK 11: Critical and subcritical experiments concerning reloading cores for KNK-II. SNEAK 11: Kritische und unterkritische Experimente zu Nachladekernen fuer KNK-II
Moellendorff, U. vonKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3464 - German - 1983
Abstract: In the Karlsruhe Fast Zero-Power Facility (SNEAK) three cores that were originally (as of 1976 to 1979) envisaged for KNK-II reloadings were investigated under the designation SNEAK 11. Two of them were built in two versions each, one with absorber rods withdrawn as usual in SNEAK assemblies and thus corresponding in critically to the burned-up power reactor, the other with absorbers about half inserted like in the fresh core. The experimental program encompassed mainly - critical size or critical insertion of the KNK regulating absorbers, - fission rate distributions, - sodium-void reactivity, - absorber worths of KNK regulating and shutdown elements. This report describes the assemblies in detail and gives the main results. It refers the reader to results that were documented earlier. (orig.)
Key words: criticality;knk-2 reactor;reactor cores;reactor lattice parameters;reactor physics;sneak reactor;subcritical assemblies
Components Category: any or undefined
display the document: 15010000.pdf
KNK-II reactor: Reload experiments in SNEAK-11 reactor. KNK II: Experimente in SNEAK 11 zu Nachladungen
Moellendorff, U. v. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)KFK--3543 - German - 1983
Abstract: Three reload cores originally planned for the KNK-II reactor were examined at the Karlsruhe Fast Zero Energy Assembly (SNEAK-reactor) under the denomination of SNEAK 11. Two of them were assembled in two versions each: with drawn absorber rods, i.e. corresponding in its criticality with spent power reactors, which is the normal SNEAK assembly. And with absorbers half-inserted as with new cores. The latter of the two in closer to the actual core design task, yet it causes great calculation problems, because they need to be mainly three-dimensional. Main points of the measuring programme included: - critical sizes (with drawn absorbers) or critical insertion depth of the KNK control/scram absorbers, - fission rate distribution, - sodium loss reactivity, - absorption values of control/scram rods and secondary shutdown units. (orig./RW)
Key words: control rod worths;criticality;knk-2 reactor;reactor kinetics;reactor lattice parameters;reactor physics;sneak reactor
Components Category: -Core components
display the document: 15028467.pdf