Simplified methods to the complete thermal and mechanical behavior of a pressure vessel during a severe accident
Creators
- 1. EDF, Moret/Loing (France)
- 2. Altran Technologies, Paris (France)
Description
EDF has developed a software package of simplified methods (proprietary ones or from literature) in order to study the thermal and mechanical behavior of a PWR pressure vessel during a severe accident involving a corium localization in the vessel lower head. Using a part of this package, the authors can evaluate for instance successively: the heat flux at the inner surface of the vessel (conductive or convective pool of corium); the thermal exchange coefficient between the vessel and the outside (dry pit or flooded pit, watertight thermal insulation or not); the complete thermal evolution of the vessel (temperature profile, melting); the possible global plastic failure of the vessel; the creep behavior in the thickness of the vessel. These simplified methods are a cost effective alternative to finite element calculations which are yet used to validate the previous methods, waiting for experimental results to come
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1778-4
- Imprint Title
- Pressure vessels and piping design, analysis, and severe accidents. PVP-Volume 331
- Imprint Pagination
- 219 p.
- Journal Page Range
- p. 145-151.
Conference
- Title
- American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 21-26 Jul 1996.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28023797
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CODES; ELECTRICITE DE FRANCE; MECHANICAL PROPERTIES; MELTDOWN; PRESSURE VESSELS; PWR TYPE REACTORS; THEORETICAL DATA; THERMAL ANALYSIS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DATA; ENRICHED URANIUM REACTORS; FRENCH ORGANIZATIONS; INFORMATION; NATIONAL ORGANIZATIONS; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-960706--.