[en] The need to consider fuel rod failures in a fast reactor safety assessment is described, covering unprotected fault conditions which force the failures by overheating of the cladding and fuel material. The physical causes and consequences of failure are identified and the way in which the key phenomena and variables are modelled in separate codes for whole core accident prediction and fuel failure experiment analysis is described. 9 refs
Anon; p. 2020-2029; 1979; p. 2020-2029; American Nuclear Society; La Grange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979