Plan on test to failure of a steel containment vessel model
Creators
- 1. Nuclear Power Engineering Corp., Tokyo (Japan)
- 2. Hitachi Works, Ibaraki-ken (Japan)
- 3. Nuclear Regulatory Commission, Rockville, MD (United States)
- 4. Sandia National Labs., Albuquerque, NM (United States)
Description
This paper describes the plan for a test to failure of a steel containment vessel model. The test specimen proposed for this test is a scale model representing certain features of an improved boiling water reactor (BWR) MARK-II containment vessel. The objective of this test is to investigate the ultimate structural behavior of the model by incrementally increasing the internal pressure, at ambient temperature, until failure occurs. Pre- and posttest analyses will be conducted to predict and evaluate the results of this test. The main objective of these analyses is to validate, by comparisons with the experimental data, the analytical methods used to evaluate the structural behavior of an actual containment vessel under severe accident conditions. This experiment is part of a cooperative program between the Nuclear Power Engineering Corporation, the United States Nuclear Regulatory Commission, and Sandia National Laboratories
Additional details
Publishing Information
- Imprint Title
- Proceedings of the fifth workshop on containment integrity
- Imprint Pagination
- 646 p.
- Journal Page Range
- p. 387-391.
- Report number
- NUREG/CP--0120
Conference
- Title
- 5. workshop on containment integrity for nuclear power plants.
- Dates
- 12-14 May 1992.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027161
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; DEFORMATION; EXPERIMENTAL DATA; FINITE ELEMENT METHOD; FISSION PRODUCT RELEASE; NONLINEAR PROBLEMS; PRESSURIZATION; RADIOACTIVE AEROSOLS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RELIABILITY; SANDIA LABORATORIES; SCALE MODELS; STEELS; TEMPERATURE DEPENDENCE; THREE-DIMENSIONAL CALCULATIONS; US NRC
- Descriptors DEC
- AEROSOLS; ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; COLLOIDS; CONTAINMENT; DATA; DISPERSIONS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; NATIONAL ORGANIZATIONS; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SAFETY; SANDIA NATIONAL LABORATORIES; SOLS; STRUCTURAL MODELS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Secondary number(s)
- SAND--92-0173; CONF-920541--.