On-line decision aid for heatup, cooldown and emergency response based on reactor vessel integrity
Description
The reactor vessel is the principal component in the nuclear steam supply system (NSSS) pressure boundary. It has irradiation embrittlement concerns not present for other components, and since it is a thick section steel body, nonductile failure modes are considered. These concerns are the basis for the 10CFR50 Rule restrictions on heatup and cooldown and for the Pressurized Thermal Shock screening criteria. Because of the critical nature of the vessel and resulting high degree of regulation, many conservatisms are placed on the limits which may become restrictive of operation. As an outgrowth of the analytical techniques used to evaluate the above concerns, an on-line system is evolving to provide the operator with direct information about the operating window available for the plant. This information is of value predominantly during heatup, cooldown and under a variety of off normal conditions affecting the vessel. This paper describes the information supplied to the operator, the applications and the use of this tool as a decision aid. The principal focus is on decision aids for the reactor operator that make it applicable as an on-line system
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Proceedings of the 1986 joint ASME/ANS nuclear power conference
- Journal Page Range
- p. 240-251.
Conference
- Title
- safe and reliable nuclear power plants.
- Acronym
- ASME/ANS bi-annual nuclear power conference
- Dates
- 20-23 Jul 1986.
- Place
- Philadelphia, PA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19005180
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; EMBRITTLEMENT; ENGINEERING; FAILURE MODE ANALYSIS; FRACTURE MECHANICS; HEATING; HUMAN FACTORS; MAN-MACHINE SYSTEMS; MANAGEMENT; MONITORING; ON-LINE CONTROL SYSTEMS; PRESSURE DEPENDENCE; PRESSURIZATION; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR OPERATION; REACTOR VESSELS; RISK ASSESSMENT; TEMPERATURE DEPENDENCE; THERMAL SHOCK
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTROL SYSTEMS; MECHANICS; ON-LINE SYSTEMS; OPERATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS