Assessment of reactor vessel integrity (ARVI)

Nuclear Engineering and Design

Volumn 235, Issue 2-4, 2005, Pages 213-232

  Sehgal, B R ^a   Karbojian, A ^a   Giri, A ^a   Kymalainen O ^b   Bonnet, J M ^c   Ikkonen, K ^a   Sairanen, R ^d   Bhandari, S ^e   Buerger, M ^f   Dienstbier, J ^g   Techy, Z ^h   Theofanous, T ⁱ  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

^b Fortum Oil and Gas Oy   (Finland)

^c DIF   (France)

^d VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

^e AREVA NP   (France)

^f USTUTT   (Germany)

^g NUCLEAR RESEARCH INSTITUTE   (Czech Republic)

^h Hungary   (Hungary)

ⁱ UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ASSESSMENT OF REACTOR VESSEL INTEGRITY (ARVI); CREEP DEFORMATION; GAP COOLING; REACTOR VESSELS;

COMPUTATIONAL FLUID DYNAMICS; COMPUTER SIMULATION; CREEP; FAILURE ANALYSIS; FINITE ELEMENT METHOD; NUCLEAR REACTOR ACCIDENTS; STRUCTURAL ANALYSIS; THERMAL LOAD;

NUCLEAR REACTORS;

EID: 19944428683     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.08.055     Document Type: Conference Paper

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