Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.019 seconds
AbstractAbstract
[en] The response of the FFTF core to protected reactivity insertion events was evaluated. Reactivity addition transients ranging from .05/cent/sub s/ to 3;/s have been considered. The evaluation method is based on a calculational model which predicts cladding strain from fuel-cladding differential thermal expansion. Comparisons made between predicted fuel damage and results of TREAT transient tests support the conservatism of the predictions. 4 refs
Primary Subject
Source
Anon; p. 1306-1315; 1979; p. 1306-1315; American Nuclear Society; LaGrange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, AIR COOLED REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FUEL ELEMENTS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, LIQUID METAL COOLED REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR PROTECTION SYSTEMS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, RESTRAINTS, SODIUM COOLED REACTORS, SOLID HOMOGENEOUS REACTORS, TEST REACTORS, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue