Experimental study of the core structure behaviour in LOCA condition
Creators
- 1. Institute of Physics and Power Engineering, Obnisnk (Russian Federation)
Description
The objective of this report is to describe the research program and its issues concerning the analysis of the in-vessel phase of accident. WWER types of materials and structures have been considered. All experiments have focused upon obtaining the data for core degradation modelling and reactor vessel strength analysis. Fuel rod ballooning and rupture under accident conditions including severe accidents, residual strength of claddings after high temperature oxidation, cladding spacer grid chemical interaction under steam presence, corium modelling, properties investigation, phase separation in melts, vessel lower head strength under high temperature loading are discussed. All of these laboratory-scale experiment are conducted in IPPE. (author). 11 figs, 2 tabs
Files
28023757.pdf
Files
(378.1 kB)
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Additional details
Publishing Information
- Imprint Title
- Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting
- Imprint Pagination
- 299 p.
- Journal Page Range
- p. 153-163.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--921
Conference
- Title
- Technical committee meeting on behaviour of LWR core materials under accident conditions.
- Dates
- 9-13 Oct 1995.
- Place
- Dimitrovgrad (Russian Federation).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28023757
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AGING; EXPERIMENTAL DATA; FRACTURE PROPERTIES; LOSS OF COOLANT; REACTOR CORES; REACTOR VESSELS; RESEARCH PROGRAMS; SIMULATION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MECHANICAL PROPERTIES; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS