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Jatuff, F.; Grimm, P.; Murphy, M.; Luethi, A.; Seiler, R.; Joneja, O.; Meister, A.; Geemert, R. van; Brogli, R.; Chawla, R.; Williams, T.; Helmersson, S.
Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety2001
Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety2001
AbstractAbstract
[en] The accurate estimation of reactor physics parameters related to the presence of cruciform absorber blades. In Boiling Water Reactors (BWR) is important for safety assessment, and for achieving a flexible operation during the cycle. Characteristics which are affected strongly include the power distribution for controlled core regions and its impact on linear heat generation rate margins, as well as the build-up of plutonium, and its influence on core excess reactivity and the reactivity worth of the shutdown system. PSI and the Swiss Nuclear Utilities (UAK) are conducting an experimental reactor physics programme related to modern Light Water Reactor (LWR) fuel assemblies, as employed in the Swiss nuclear power plants: the so-called. LWR-PROTEUS Phase I project. A significant part of this project has been devoted to the characterization of highly heterogeneous BWR fuel elements in the presence of absorber blades. The paper presents typical results for the performance of modern lattice codes in the estimation of controlled assembly reaction rate distributions, the sensitivity to the geometrical and material characterization, and a preliminary comparison of reflected-test-zone calculations with experimental reaction rate distributions measured in a Westinghouse SVEA-96+ assembly under full-density water moderation conditions in the presence of Westinghouse boron-carbide absorber blades. (author)
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Smith, Brian; Gschwend, Beatrice (eds.); Paul Scherrer Inst., CH-5232 Villigen PSI (Switzerland); 140 p; ISSN 1423-7342;
; Mar 2001; p. 25-32; 8 figs., 1 tab., 10 refs.

Record Type
Report
Literature Type
Numerical Data; Progress Report
Report Number
Country of publication
DATA, DOCUMENT TYPES, ENRICHED URANIUM REACTORS, GRAPHITE MODERATED REACTORS, INFORMATION, NUCLEAR FACILITIES, NUMERICAL DATA, POWER PLANTS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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