Pressurization test on the full scale equipment hatch model
- 1. Nuclear Power Engineering Corp., Tokyo (Japan)
Description
In order to evaluate the behavior for structural discontinuous flange portion in containment vessels during severe accident condition, the full-scale test model, simulating the equipment hatch in BWR containment vessel, has been manufactured and the pressurization test has been conducted. The test model has been pressurized up to leakage initiation with hydrostatic pressure to understand the behavior and pressure-proof limit in the flange portion. The measuring points were about 300 channels, including strain gages, displacement transducers, temperature and pressure sensors. The leakage onset in the flange portion occurred at 19.5kg/cm2. This paper described the test results including the test procedure and comparison between the measured data and analysis results focusing on the flange opening displacement, bolt strain and flange ring strain. In addition, preliminary analyses were performed to predict the structural behavior of the model using finite element models of ANSYS code. With regard to the analysis results, the flange opening displacement and flange ring strain were well predicted below 15kg/cm2, and the average bolt strain was well predicted. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the workshop on severe accident research held in Japan (SARJ-97)
- Imprint Pagination
- 513 p.
- Journal Page Range
- p. 198-202
- Report number
- JAERI-Conf--98-009
Conference
- Title
- workshop on severe accident research held in Japan
- Acronym
- SARJ-97
- Dates
- 6-8 Oct 1997
- Place
- Yokohama (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29065738
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CONTAINMENT; FASTENERS; FINITE ELEMENT METHOD; FLANGES; PRESSURIZATION; REACTOR ACCIDENTS; REACTOR VESSELS; RELIABILITY; STEELS; STRAIN GAGES
- Descriptors DEC
- ACCIDENTS; ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; EVALUATION; IRON ALLOYS; IRON BASE ALLOYS; MEASURING INSTRUMENTS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS