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Cladding metallurgy and fracture behavior during reactivity-initiated accidents at high burnup [electronic resource].

Published:
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
15 pages : digital, PDF file
Additional Creators:
Argonne National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
High-burnup fuel failure during a reactivity-initiated accident has been the subject of safety-related concern. Because of wide variations in metallurgical and simulation test conditions, it has been difficult to understand the complex failure behavior from major tests in NSRR and CABRI reactors. In this paper, a failure model based on fracture toughness and microstructural characteristics is proposed in which fracture toughness of high-burnup cladding is assumed to be sensitive to temperature and exhibit ductile-brittle transition phenomena similar to those of irradiated bcc alloys. Significant effects of temperature and shape of the pulse are predicted when a simulated test is conducted near the material`s transition temperature. Temperature dependence of fracture toughness is, in turn, sensitive to cladding microstructure such as density, distribution, and orientation of hydrides, oxygen distribution in the metallic phase, and irradiation-induced damage. Because all these factors are strongly influenced by corrosion, the key parameters that influence susceptibility to failure are oxide layer thickness and hydriding behavior. Therefore, fuel failure is predicted to be strongly dependent on cladding axial location as well as on burnup. 10 figs, 21 refs.
Report Numbers:
E 1.99:anl/et/cp--91397
E 1.99: conf-970315--3
conf-970315--3
anl/et/cp--91397
Subject(s):
Other Subject(s):
Note:
Published through SciTech Connect.
12/01/1996.
"anl/et/cp--91397"
" conf-970315--3"
"DE97004700"
ANS international topical meeting on light water reactor fuel performance, Portland, OR (United States), 2-6 Mar 1997.
Chung, H.M.; Kassner, T.F.
Funding Information:
W-31-109-ENG-38
View MARC record | catkey: 14364716