French RPV PTS assessment: an overview of EDF research and development in progress on thermalhydraulic, materials and mechanical aspects
Creators
- 1. Electricite de France, Research and Development Division, MMC Department, Site des Renardieres, Moret-sur-Loing cedex (France)
- 2. Electricite de France, Generation and Transmission Division, DPN, Saint-Denis cedex (France)
- 3. Electricite de France, Engineering and Construction Division, SEPTEN, Villeurbanne cedex (France)
- 4. Electricite de France, Research and Development Division, MFTT Department, Chatou cedex (France)
Description
A significant extensive Research and Development work is conducted by Electricite de France (EDF) related to the structural integrity re-assessment of the French 900 and 1300 MWe reactor pressure vessels in order to increase their lifetime. Within the framework of this programme, numerous developments have been implemented or are in progress related to the methodology to assess flaws during a pressurized thermal shock (PTS) event. The paper contains three aspects: a short description of the specific French approach for RPV PTS assessment, a presentation of recent improvements on thermalhydraulic, materials and mechanical aspects, and finally an overview of the present R and D programme on thermalhydraulic, materials and mechanical aspects. Regarding the last aspect on present R and D programme, several projects in progress will be shortly described. This overview includes the redefinition of some significant thermalhydraulic transients based on some new three-dimensional CFD computations (focused at the present time on small break LOCA transient), the assessment of vessel materials properties, and the improvement of the RPV PTS structural integrity assessment including several themes such as warm pre-stress (WPS), crack arrest, constraint effect. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-116403-3
- Imprint Title
- Nuclear power plant life management. Proceedings of a symposium
- Imprint Pagination
- 976 p.
- Journal Issue
- no. 21/CD
- Series
- C and S papers series
- Journal Page Range
- p. 264-294
- ISSN
- 1562-4153
- Report number
- IAEA-CSP--21/CD
Conference
- Title
- Symposium on nuclear power plant life management
- Dates
- 4-8 Nov 2002
- Place
- Budapest (Hungary)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35052169
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFECTS; FINITE DIFFERENCE METHOD; LOSS OF COOLANT; MECHANICAL PROPERTIES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR MATERIALS; RESEARCH PROGRAMS; STRESS ANALYSIS; THERMAL HYDRAULICS; THERMAL SHOCK; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; ITERATIVE METHODS; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 27 refs, 18 figs, tabs Imprint:Data in PDF format
- Secondary number(s)
- IAEA-CN--92/36