NRC research in aging and extended life for LWR primary systems
The US Nuclear Regulatory Commission (NRC) research program on the integrity of materials and components for light water reactor (LWR) primary systems has always had a primary objective of identifying and evaluating issues that could affect the safety of operating nuclear power plants. Studies to date have focused on safety assurance for regulation during the original 40-yr license period. As some of these earliest licenses begin to approach their end, both NRC and the industry are attempting to detect and evaluate issues that may impact on safe and reliable life for an additional operating period of up to 40 yr. The NRC expects to receive the first application for plant life extension in 1992; thus, the technical issues of critical importance for regulatory review must be identified and an adequate, independent basis established by then. Neutron-induced embrittlement of the reactor vessel irradiation effects to core structural elements. An issue that bridges both vessels and piping is that of the fatigue life, as currently described in Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, toughness decrease in cast stainless steel due to aging at service temperature, water chemistry, and nondestructive examination are issues that affect aging and life extension discussed in the paper.
- OSTI ID:
- 6928847
- Report Number(s):
- CONF-8711195-; TRN: 88-028655
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
- Country of Publication:
- United States
- Language:
- English
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PRIMARY COOLANT CIRCUITS
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RESEARCH PROGRAMS
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PIPES
PRESSURE VESSELS
REACTOR CORES
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REACTOR SAFETY
STEAM GENERATORS
WATER CHEMISTRY
BOILERS
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WATER COOLED REACTORS
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