Reduction of pressure vessel neutron fluence - Industry response to 10CFR50.61
Description
Certain overcooling transients with overpressurization can result in increased pressure vessel stress fields, which increase the probability of failure. The conditions that contribute to vessel damage in these pressurized thermal shock (PTS) events are vessel embrittlement due to fast neutron irradiation and the existence of flaws on the inside surface of the pressure vessel. On July 23, 1985, the US Nuclear Regulatory Commission (NRC) added the PTS rule 50.61 to the Code of Federal Regulations (CFR) in a section entitled Fracture Toughness Requirements for Protection Against Thermal Shock Events. While most plants have sufficient pressure vessel toughness, several pressurized water reactor plants required a significant reduction of the vessel irradiation rate to meet the requirements of 10CFR50.61. The collective industry response to meet the 10CFR50.61 requirements via flux reduction is discussed
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 430-431
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036694
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BNL; BWR TYPE REACTORS; EMBRITTLEMENT; FAILURES; FAST NEUTRONS; FRACTURE MECHANICS; FUEL ASSEMBLIES; FUEL MANAGEMENT; IRRADIATION; NEUTRON FLUENCE; NEUTRON LEAKAGE; PRESSURE VESSELS; PRESSURIZATION; PROBABILITY; PWR TYPE REACTORS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; SERVICE LIFE; SHIELDING; THERMAL SHOCK; US NRC
- Descriptors DEC
- BARYONS; CONTAINERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; LIFETIME; MANAGEMENT; MECHANICS; NATIONAL ORGANIZATIONS; NEUTRONS; NUCLEAR MATERIALS MANAGEMENT; NUCLEONS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.