A structured approach to evaluating aging of the advanced test reactor
Description
An aging evaluation program has been developed for the United States Department of Energy's Advanced Test Reactor to support the current goal of operation through the year 2014 and beyond. The Aging Evaluation and Life Extension Program (AELEX) employs a three-phased approach. In Phases 1 and 2, now complete, components were identified, categorized and prioritized. Critical components were selected and aging mechanisms for the critical components identified. An initial evaluation of the critical components was performed and extended life operation for the plant appears to be both technically and economically feasible. Detailed evaluations of the critical components are now in progress in the early stages of Phase 3. Some results are available. Evaluations of many non-critical components and refinements to the program based on probabilistic risk assessment results will follow in later stages of Phase 3. 6 refs., 2 figs., 5 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE91001937; OSTI; INIS; US Govt. Printing Office Dep.Files
22019579.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- EGG-M--90054
Conference
- Title
- American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities.
- Dates
- 30 Sep - 3 Oct 1990.
- Place
- Boise, ID (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22019579
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; ATR REACTOR; EVALUATION; LIFETIME; REACTOR COMPONENTS; RISK ASSESSMENT
- Descriptors DEC
- ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-900917--21.