Published 1994
| Version v1
Book
Ageing of structural materials in the core domain of the reactor pressure vessel
Description
In this discussion, ageing mechanisms on the basis of examples are described. These originate from: - mainly mechanical loading (e.g. fatigue), -overlaying the mechanical loading with radiation, - corrosive loading (e.g. inter-crystalline stress crack corrosion), - overlaying the corrosive loading with radiation (radiation induced stress crack corrosion). Their effects on components within the core region of the reactor pressure vessel are discussed. 6 figs., 2 tabs., 8 refs
Additional details
Additional titles
- Original title (German)
- Alterung von Strukturwerkstoffen im Kernbereich des RDB
Publishing Information
- Publisher
- Schweizerische Vereinigung fuer Atomenergie (SVA).
- Imprint Place
- Bern (Switzerland)
- Imprint Title
- SVA further education course: ageing in nuclear power plants. Proceedings
- Imprint Pagination
- [430 p.].
- Journal Page Range
- p. 2.1-1-2.1-13.
Conference
- Title
- ageing in nuclear power plants.
- Original Conference Title
- SVA-Vertiefungskurs: Alterungsmanagement bei Kernkraftwerken
- Acronym
- SVA further education course
- Dates
- 2-4 Nov 1994.
- Place
- Winterthur (Switzerland).
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 26021924
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AGING; AUSTENITIC STEELS; EXPERIMENTAL DATA; FATIGUE; FERRITIC STEELS; FRACTURE MECHANICS; GREIFSWALD-1 REACTOR; KOZLODUY-2 REACTOR; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CONTAINERS; CORROSION; DATA; ENRICHED URANIUM REACTORS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; RADIATION FLUX; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:SVA-Vertiefungskurs: Alterungsmanagement bei Kernkraftwerken. Kursreferate.