Resolution of the reactor vessel materials toughness safety issue; Task Action Plan A-11; main report and Appendixes A and B
The central problem in the Unresolved Safety Issue A-11, 'Reactor Vessel Materials Toughness,' was to provide guidance in performing analyses for reactor pressure vessels (RPVs) which fail to meet the toughness requirements during service life as a result of neutron radiation embrittlement. 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 has been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the RPV fracture problem with assumed beltline region flaws. Volume I of this report is a brief presentation of the problem and the results; Volume II provides the detailed technical foundations.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
- OSTI ID:
- 5486076
- Report Number(s):
- NUREG-0744-V1
- Country of Publication:
- United States
- Language:
- English
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