Falsire: CSNI project for fracture analyses of large-scale international reference experiments (Phase 1). Comparison report
Description
A summary of the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE) is presented. Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI), formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear vessel components. The aim of the Project FALSIRE was to assess various fracture methodologies through interpretive analyses of selected large-scale fracture experiments. The six experiments used in Project FALSIRE (performed in the Federal Republic of Germany, Japan, the United Kingdom, and the U.S.A.) were designed to examine various aspects of crack growth in reactor pressure vessel (RPV) steels under pressurized-thermal-shock (PTS) loading conditions. The analysis techniques employed by the participants included engineering and finite-element methods, which were combined with Jr fracture methodology and the French local approach. For each experiment, analysis results provided estimates of variables such as crack growth, crack-mouth-opening displacement, temperature, stress, strain, and applied J and K values. A comparative assessment and discussion of the analysis results are presented; also, the current status of the entire results data base is summarized. Some conclusions concerning predictive capabilities of selected ductile fracture methodologies, as applied to RPVs subjected to PTS loading, are given, and recommendations for future development of fracture methodologies are made
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Additional details
Publishing Information
- Imprint Pagination
- 162 p.
- Report number
- NEA-CSNI-R--1994-12
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 41025195
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COORDINATED RESEARCH PROGRAMS; CRACK PROPAGATION; CRACKS; EMBRITTLEMENT; FRACTURE MECHANICS; FRACTURE PROPERTIES; MATERIALS TESTING; PRESSURE VESSELS; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; RISK ASSESSMENT; STEELS; STRESS ANALYSIS; STRESSES; TENSILE PROPERTIES; THERMAL SHOCK
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; EVALUATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICS; RESEARCH PROGRAMS; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 50 refs.