Probabilistic safety assessment event tree analysis of radioactive release risk for pool type sodium-cooled fast reactor
Description
The safety characteristics and radioactive release mechanism of pool type sodium-cooled fast reactor (SFR) are significantly different from those of pressurized water reactor. Under the new nuclear safety requirements, the research on probabilistic safety assessment (PSA) of radioactive release risk for SFR is urgently needed. Taking the pool type SFR as the research object, the main position and mode of large radioactive release were identified and the radioactive release event trees were constructed by analyzing the radioactive source, the containment boundary and the severe accident that might challenge the integrity of the containment boundary. The results can serve as reference for further research on PSA of radioactive release risk for pool type SFR. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 54
- Journal Issue
- 7
- Journal Page Range
- p. 1228-1234
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55097288
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT; FAILURE MODE ANALYSIS; HAZARDS; PONDS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RADIATION PROTECTION; RADIATION SOURCES; RISK ASSESSMENT; SAFETY; SEVERE ACCIDENTS; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTORS; SURFACE WATERS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 6 tabs., 14 refs.; http://dx.doi.org/10.7538/yzk.2019.youxian.0445