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Morman, J.A.; Tentner, A.M.; Dever, D.J.
Argonne National Lab., IL (USA)1985
Argonne National Lab., IL (USA)1985
AbstractAbstract
[en] The validation of the SAS4A accident analysis code centers on its capability to calculate the wide range of tests performed in the TREAT (Transient Reactor Test Facility) in-pile experiments program. This paper presents the SAS4A analysis of a simulated TUCOP (Transient-Under-Cooled-Over-Power) experiment using seven full-length PFR mixed oxide fuel pins in a flowing sodium loop. Calculations agree well with measured thermal-hydraulic, pin failure time and post-failure fuel motion data. The extent of the agreement confirms the validity of the models used in the SAS4A code to describe TUCOP accidents
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Source
1985; 6 p; ANS/ENS fast reactor safety meeting; Knoxville, TN (USA); 21-24 Apr 1985; Available from NTIS, PC A02/MF A01; 1 as DE85011473
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, AIR COOLED REACTORS, ALKALI METALS, BREEDER REACTORS, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS, METALS, NUCLEAR FUELS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SOLID FUELS, SOLID HOMOGENEOUS REACTORS, TEST REACTORS, THERMAL REACTORS
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