Ductility of zircaloy-4 fuel cladding and guide tubes at high fluences

ASTM Special Technical Publication

Volumn , Issue 1467, 2005, Pages 604-631

  Yagnik, Suresh K ^a   Hermann, Armin ^a   Kuo, Roang Ching ^a   Barberis, P ^b   White, J ^c   Mahmood, S ^d   Garde, A ^e   Bouffioux, P ^f   Kim, Y S ^g  

^a ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^b CEZUS   (France)

^c LOCKHEED MARTIN   (United States)

^d Global Nuclear Fuel   (United States)

^e Westinghouse ^*  (United States)

^f EDF R AND D   (France)

^g Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Ductility; Fluence; Hydriding; Mechanical tests; Stress strain; Zircaloy 4

Indexed keywords

BOILING WATER REACTORS; DUCTILITY; HYDRIDES; HYDROGEN; MECHANICAL TESTING; NEUTRONS; NUCLEAR FUEL CLADDING; SCANNING ELECTRON MICROSCOPY;

FLUENCE; HYDRIDING; STRESS-RELIEF ANNEALED (SRA); STRESS-STRAIN; ZIRCALOY FUEL CLADDING;

ZIRCONIUM ALLOYS;

EID: 33744815224     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (15)

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