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Proceedings of the International Conference on Nuclear Engineering (ICONE12)

Volumn 1, Issue , 2004, Pages 605-614

Application of the PDM (point defect model) to the oxidation of zircaloy fuel cladding in water-cooled nuclear reactors

(3) Park, Pilyeon a Urquidi Macdonald, Mirna a Macdonald, Digby D b

a The Pennsylvania State University (United States)

b PENNSYLVANIA STATE UNIVERSITY (United States)

Author keywords

Hydride; Oxide; Passive film; Water cooled nuclear reactor; Zircaloy fuel cladding

Indexed keywords

ELECTRIC POTENTIAL; HYDRIDES; INTERFACES (MATERIALS); OXIDATION; OXIDES; PH EFFECTS; POINT DEFECTS; POROSITY;

BARRIER LAYERS; PASSIVE FILM; WATER-COOLED NUCLEAR REACTOR; ZIRCALOY FUEL CLADDING;

WATER COOLED REACTORS;

EID: 10644255431 PISSN: None EISSN: None Source Type: Conference Proceeding
DOI: 10.1115/icone12-49098 Document Type: Conference Paper

Times cited : (6)

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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.