The development of a stress analysis code for nuclear graphite components in gas-cooled reactors

Journal of Nuclear Materials

Volumn 350, Issue 3, 2006, Pages 208-220

  Tsang, D K L ^a   Marsden, B J ^a  

^a UNIVERSITY OF MANCHESTER   (United Kingdom)

Author keywords

C0100; M0200; M0300

Indexed keywords

CHEMICAL REACTORS; COOLING; GRAPHITE; NEUTRON IRRADIATION; NUCLEAR ENERGY; OXIDATION; RADIOLYSIS;

C0100; M0200; M0300;

STRESS ANALYSIS;

EID: 33646041303     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2006.01.015     Document Type: Article

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