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A transient failure model for zircaloy cladding

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5968488
; ;
None
Research Organization:
ANATECH International Corporation, 3344 N. Torrey Pines Court, number320, La Jolla, CA 92037
OSTI ID:
5968488
Report Number(s):
CONF-821103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 43
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ALLOYS
CHEMICAL REACTIONS
CORROSION
CREEP
CRITICAL TEMPERATURE
FAILURE MODE ANALYSIS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
MECHANICAL PROPERTIES
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTOR TECHNOLOGY
STRESS CORROSION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMODYNAMIC PROPERTIES
TIN ALLOYS
TRANSIENTS
TRANSITION TEMPERATURE
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS