Structural shock tests of prototype FBR 'MONJU' scale models
- 1. Tokyo Shibaura Electric Co. Ltd., Kawasaki, Kanagawa (Japan). Research and Development Center
- 2. Atomic Power Department, Toshiba, Tsurumiku, Yokohama, Japan
- 3. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
- 4. Tokyo Univ. (Japan). Faculty of Engineering
Description
This paper presents some results of experiments which simulate the structural dynamic response of a LMFBR primary coolant boundary to a hypothetical core disruptive accident (HCDA) based on scale models and high explosives. It was noted that high explosives are no longer a good simulant of the HCDA. However, the main purpose of the program, which included this experiment, is not to experimentally predict the dynamic response of the reactor structure at the HCDA, but to validate computer codes, which describe the pressure wave propagation and damage process in the reactor structures, using data obtained from these model experiments. The experiments were undertaken using many 1/15 scale simple models of the reactor vessels and internal structures, as well as 1/15 and 1/7.5 scale complex models of the interim design of prototype LMFBR 'MONJU'. Simple model experiments involved a series of shock tests using pentolite to investigate the configuration effects of the vessel restraining section, the dipped-plate effect and the core barrel effect, respectively. (Auth.)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 38
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 109-129
- ISSN
- 0029-5493
Conference
- Title
- International seminar on extreme load conditions and limit analysis procedures for structural reactor safeguards and containment structures.
- Dates
- 8 Sep 1975.
- Place
- Berlin, Germany.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8301868
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LMFBR TYPE REACTORS; MONJU REACTOR; PRIMARY COOLANT CIRCUITS; REACTOR CORE DISRUPTION; REACTOR SAFETY EXPERIMENTS; REACTOR SIMULATORS; REACTOR VESSELS; STRAINS; STRUCTURAL MODELS; TESTING
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; BREEDER REACTORS; CONTAINERS; COOLING SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUNCTIONAL MODELS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent