VTESTER analysts manual
Creators
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Nuclear and Advanced Technology Div.
- 2. Decision Focus, Inc., Mountain View, CA (United States)
Description
Neutron irradiation from reactor operation is known to cause embrittlement in reactor pressure vessel materials. In some nuclear power plants, the effects of irradiation damage could make the reactor pressure vessel the limiting component when considering extended plant life. EPRI has developed the VTester Code as a tool for utilities in addressing the embrittlement issues and choosing possible actions to mitigate the effects of vessel embrittlement on future plant operation. VTester makes use of Decision Analysis techniques in performing a cost/benefit evaluation of various options for managing embrittlement issues. The VTester code and an associated User's Manual has been published by EPRI in the EPRIGEMS format (NP-7020-CCML). This Analyst's Manual is a supporting document which discusses the issues and the mitigative options to address radiation embrittlement of reactor vessels. This report also briefly addresses the development of influence diagrams, decision trees which integrates the uncertainties associated with engineering, regulatory and economic variables into a comprehensive framework for evaluating alternative mitigative actions
Availability note (English)
Available from EPRI Distribution Center, 207 Coggins Drive, PO Box 23205, Pleasant Hill, CA 94523.Additional details
Additional titles
- Subtitle (English)
- Final report
Publishing Information
- Imprint Pagination
- 89 p.
- Report number
- EPRI-TR--100465
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25018768
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ANNEALING; EMBRITTLEMENT; FRACTURE PROPERTIES; FUEL MANAGEMENT; IRRADIATION; NEUTRON FLUX; NEUTRON REFLECTORS; PRESSURE VESSELS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; RISK ASSESSMENT; SHIELDING; STEELS; THERMAL SHOCK; V CODES; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MANAGEMENT; MECHANICAL PROPERTIES; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Electric Power Research Inst., Palo Alto, CA (United States).