Analysis of ductile fracture in zircaloy cladding tubes
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6647969
None
- Research Organization:
- Nippon Nuclear Fuel Development Corp., 2163 Narita-machi, Oarai-machi Ibaraki 311-13
- OSTI ID:
- 6647969
- Report Number(s):
- CONF-840614-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 46; ISSN TANSA
- 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
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
FAILURES
FRACTURE MECHANICS
FRACTURES
FUEL CANS
FUEL-CLADDING INTERACTIONS
MECHANICS
STRESS INTENSITY FACTORS
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
FAILURES
FRACTURE MECHANICS
FRACTURES
FUEL CANS
FUEL-CLADDING INTERACTIONS
MECHANICS
STRESS INTENSITY FACTORS
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS