Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.018 seconds
Ruther, W.E.; Staffou, J.D.; Chopra, P.S.; Lambert, J.D.B.; Srinivas, S.
Structural mechanics in reactor technology1977
Structural mechanics in reactor technology1977
AbstractAbstract
[en] Permanent deformation and fracture of subassembly ducts due to potential pressure pulses generated by the discharge of fission gas from fuel elements are important considerations in determining the burnup limit of fuels in LMFBR's. This paper discusses the results of a series of dynamic pressure tests that were conducted on intentionally defected irradiated EBR-II subassembly ducts. The tests were designed to simulate failure of a fuel element in a cluster of such elements. The major objective of the tests was to provide complete assurance that cladding failure of a driven-fuel element, which might conceivably cause rapid release of stored fission gas, would not deform or otherwise damage subasembly ducts in a way that would hinder movement of a control rod. The test program described provides a reliable method of assessing the failsafety of LMFBR ducts. The test procedure is particularly important since present analytical solutions cannot adequately model the subassembly and the reactor conditions. (Auth.)
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); v. D p. D3/7 1-8; ISBN 0 444 85062 7;
; 1977; v. D p. D3/7 1-8; North-Holland; Amsterdam, Netherlands; 4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977

Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, BREEDER REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FLUIDS, ISOTOPES, LIQUID METAL COOLED REACTORS, MECHANICAL PROPERTIES, POWER REACTORS, RADIATION EFFECTS, RADIOACTIVE MATERIALS, REACTOR ACCIDENTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue