Review of PRA methodology for LMFBR
Description
Probabilistic Risk Assessment (PRA) has been widely used as a tool to evaluate the safety of NPPs (Nuclear Power Plants), which are in the design stage as well as in operation. Recently, PRA becomes one of the licensing requirements for many existing and new NPPs. KALIMER is a Liquid Metal Fast Breeder Reactor (LMFBR) being developed by KAERI. Since the design concept of KALIMER is similar to that of the PRISM plant developed by GE, it would be appropriate to review the PRA methodology of PRISM as the first step of KALIMER PRA. Hence, in this report summarizes the PRA methodology of PRISM plant, and the required works for the PSA of KALIMER based on the reviewed results. The PRA technology of PRISM plant consists of following five major tasks: (1) development of initiating event list, (2) development of system event tree, (3) development of core response event tree, (4) development of containment response event tree, and (5) consequences and risk estimation. The estimated individual and societal risk measures show that the risk from a PRISM module is substantially less than the NRC goal. Each task is compared to the PRA methodology of Light Water Reactor (LWR)/Pressurized Heavy Water Reactor (PHWR). In the report, each task of PRISM PRA methodology is reviewed and compared to the corresponding part of LWR/PHWR PSA performed in Korea. The parts that are not modeled appropriately in PRISM PRA are identified, and the recommendations for KALIMER PRA are stated. (author). 14 refs., 9 tabs., 4 figs
Availability note (English)
Available from INIS in electronic formFiles
30056073.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- KAERI/AR--524/99
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 30056073
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CODES; DESIGN; LMFBR TYPE REACTORS; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SAFETY; THERMAL POWER PLANTS