Published 1997
| Version v1
Report
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The state of the art of WWER type RPV: radiation embrittlement and mitigation
Description
The main activities concerning the state of art of WWER type pressure vessels included validation of empirical relationships between irradiation embrittlement and chemical composition as well as temperature, fluence and flux; validation of annealing regime; determination of initial mechanical properties and evaluation of actual material properties of the operating WWER-440/230 NPP pressure vessels. Concern tasks for life management of WWER-440 (models 230 and 231) and WWER 1000 were defined, based on the obtained results
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Additional details
Publishing Information
- Imprint Title
- Irradiation effects and mitigation. Proceedings of the IAEA Specialists Meeting. Working material
- Imprint Pagination
- 398 p.
- Journal Page Range
- p. 23-41
- Report number
- IWG-LMNPP--97/2
Conference
- Title
- IAEA specialists meeting on irradiation effects and mitigation
- Dates
- 15-19 Sep 1997
- Place
- Vladimir (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 29056105
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; ANNEALING; CHEMICAL COMPOSITION; EMBRITTLEMENT; MATERIALS TESTING; MITIGATION; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; TRANSITION TEMPERATURE; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; JOINTS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Figs