Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Appendices C-K. [PWR; BWR]

Technical Report · Fri Oct 01 04:00:00 EDT 1982

OSTI ID:6675549

The central problem in the unresolved safety issue A-11, Reactor Vessel Materials Toughness, was to provide guidance in performing analyses required by 10 CFR Part 50, Appendix G, Section V.C. for reactor pressure vessels (RPVs) which fail to meet the toughness requirement during service life as a result of neutron radiation embrittlement. Although the methods of linear-elastic fracture mechanics (LEFM) were adequate for low-temperature RPV problems, they were inapplicable under operating conditions because vessel steels, even those which exhibit less than 50 ft-lb of C/sub v/ energy, were relatively tough at temperatures where the impact energy reached its upper shelf values. A technical team of recognized experts was organized to assist the NRC staff in addressing the problem. Using the foundation of the tearing modulus concept, which had been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the problem of RPV fracture with assumed beltline region flaws. The first paper of this report is a summary of the problem, the solutions, and the results of verification analyses. The details are provided in a series of appendices in Volumes I and II.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
• OSTI ID: 6675549
• Report Number(s): NUREG-0744-Vol.2-Rev.1; ON: DE83900470
• Country of Publication: United States
• Language: English

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