Published December 1996 | Version v1
Report Open

Experimental study of the core structure behaviour in LOCA condition

  • 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

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Part of:
Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting

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

Optional Information