A probabilistic approach to assessing AGR core life

Nuclear Energy

Volumn 35, Issue 1, 1996, Pages 15-23

  McLachlan, N ^a   Szczepura, R T ^a   Davies, M A ^b   Judge, R C B ^b   Marsden, B J ^a  

^a Nuclear Electric ^*

^b RICARDO UK LTD   (United Kingdom)

Author keywords

[No Author keywords available]

Indexed keywords

CORE LIFE; CORE SAFETY; GRAPHITE CORE COMPONENTS; PROBABILISTIC ANALYSIS;

ACCIDENT PREVENTION; AGING OF MATERIALS; COMPUTER AIDED ANALYSIS; FAILURE (MECHANICAL); FINITE ELEMENT METHOD; GAS COOLED REACTORS; GRAPHITE; IRRADIATION; PROBABILITY; RADIATION EFFECTS; SERVICE LIFE; STATISTICAL METHODS;

REACTOR CORES;

EID: 0030086904     PISSN: 01404067     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (2)

1. KELLY B. T. Nuclear reactor moderator materials. Mat. Sci. Tech., 1994, 10A.
2. LOSTY H. H. W. and ORCHARD J. S. The strength of graphite. Proceedings of the 5th conference on carbon. Pennsylvania, Vol I, 1961.