Published January 1988 | Version v1
Journal article

Utilization survey of PRAISE-B, reactor piping reliability assessment code, based on probabilistic fracture mechanics

  • 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.

Description

In the United States, in order to obtain better evaluation of the reliability of nuclear components, several codes, based on probabilistic fracture mechanics, have already been developed. One of these codes, PRAISE-B (Piping Reliability Assessment Including Seismic Event), has been surveyed for more efficient utilization, and the following conclusions have been obtained. (1) PRAISE-B requires only simple input, yet contains various functions for piping failure probability evaluation. (2) Tearing modulus instability as well as plastic collaps should be taken into consideration as failure criteria when the code is applied to LBB (leak-before-break) assessment. (author)

Additional details

Publishing Information

Journal Title
Denryoku Chuo Kenkyusho Hokoku
Journal Issue
no.T87012
Series
Denryoku Chuo Kenkyusho Hokoku.
CODEN
DCKHD