Published 1990
| Version v1
Book
The lifespan of nuclear reactor pressure vessels
Description
The main degradation mechanisms of a PWR reactor pressure vessel is irradiation embrittlement. The limiting criterion will be either the RTNDT of the inside surface of the vessel, submitted to the maximum neutron flux, or the decrease in upper shelf energy level (mainly for older US plants). For older pressure vessels, this embrittlement could reduce the life of the vessel, and when a high embrittlement is expected, a flux reduction program implemented soon enough could be an effective mitigating measure. When no other solution is available, an anneal of the pressure vessel seems to be feasible and would allow to restore partially its properties. (author) 8 figs., 1 tab., 13 refs
Additional details
Additional titles
- Original title (no language)
- SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken.
Publishing Information
- Publisher
- Schweizerische Vereinigung fuer Atomenergie (SVA).
- Imprint Place
- Bern (Switzerland)
- Imprint Title
- SVA further education course: power upgrading and lifespan expansion of nuclear power plants
- Imprint Pagination
- vp.
- Journal Page Range
- p. C-2.1-C-2.15.
Conference
- Title
- power upgrading and lifespan expansion of nuclear power plants.
- Original Conference Title
- SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken
- Acronym
- SVA further education course
- Dates
- 25-27 Apr 1990.
- Place
- Brugg-Windisch (Switzerland).
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 23067921
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ANNEALING; CHARPY TEST; CRACK PROPAGATION; EMBRITTLEMENT; EXPERIMENTAL DATA; LIFETIME; MONITORING; NEUTRON FLUX; PRESSURE VESSELS; STRAIN AGING; THERMAL SHOCK
- Descriptors DEC
- AGING; CONTAINERS; DATA; DESTRUCTIVE TESTING; HEAT TREATMENTS; IMPACT TESTS; INFORMATION; MATERIALS TESTING; MECHANICAL TESTS; NUMERICAL DATA; RADIATION FLUX; TESTING
Optional Information
- Notes
- Imprint:SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken.