The radioactive release path and release category analysis of fluoride salt-cooled high temperature reactor
- 1. Nuclear and Radiation Safety Center, MEP, Beijing (China)
Description
The probabilistic safety assessment (PSA) is more and more important in the safety analysis of reactor. Because the design concept of FHR is very different with the PWR, its PSA method is unique. In the previous study, the PSA framework of FHR has been discussed. The level one and level two PSA will be combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release category will be the target. Finally, the level three PSA will be done. Also the initiating events list, the type of accident event and the source terms have been studied. The radioactive release path and the release category is one of the most important steps, and they are also the results of the PSA of FHR. Base on the studied results and the FHR design in China, the safety function of the sub-system will be discussed. Then the possible release path and release source term will be inference analyzed by the logic diagram method. Finally, based on the type of accident, source terms and mitigation methods, the release category of FHR will be analyzed and definition. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of Asian symposium on risk assessment and management (ASRAM 2017)
- Imprint Pagination
- 575 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Asian symposium on risk assessment and management
- Acronym
- ASRAM 2017
- Dates
- 13-15 Nov 2017
- Place
- Yokohama, Kanagawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50008242
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COATED FUEL PARTICLES; FISSION PRODUCT RELEASE; FLUORIDES; HEAT EXCHANGERS; HTR REACTOR; MOLTEN SALT FUELED REACTORS; PROBABILISTIC ESTIMATION; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR DESIGN; REACTOR SAFETY; REACTOR VESSELS; RISK ASSESSMENT; SOURCE TERMS; SUPERCRITICAL STATE
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; CONTAINERS; CONTROL SYSTEMS; COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FUELED REACTORS; FLUORINE COMPOUNDS; FUEL PARTICLES; HALIDES; HALOGEN COMPOUNDS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MOLTEN SALT REACTORS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SEVERE ACCIDENTS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Folder Name: FullPaper, Paper ID: ASRAM2017-1024.pdf; 21 refs., 4 figs., 3 tabs.