Development of source term evaluation method applicable to dynamic PRA
- 1. Central Research Institute of Electric Power Industry, Nuclear Technology Research Laboratory, Yokosuka, Kanagawa (Japan)
- 2. Tokyo University, School of Engineering, Department of Nuclear Engineering and Management, Tokyo (Japan)
Description
The objective of this study is to develop a source term evaluation method applicable to a dynamic probabilistic risk assessment (PRA) for a level 2 PRA. The dynamic PRA for a level 2 PRA needs a method that can calculate the behaviors of fission products (FPs) in nuclear power plants (NPPs) during a severe accident (SA) appropriately with much a smaller calculation load than that of existing SA analysis methods. In this study, a new method called the source term phenomenological relationship diagram (PRD) is developed by applying the PRD method. The source term PRD consists of the major phenomena related to FP behaviors and their quantification processes. The trial evaluation of the method is conducted for a long-term station blackout scenario. The FP behaviors evaluated using the source term PRD are consistent with those obtained by the conventional SA analysis with a much smaller computational load than that of the conventional SA analysis methods. These facts verify that the source term PRD is applicable to a level 2 dynamic PRA. In the future, the analysis of the source term PRD coupled with thermal hydraulic analysis will be conducted for the establishment of the level 2 dynamic PRA. (author)
Availability note (English)
Available from https://doi.org/10.3327/taesj.J18.039Additional details
Additional titles
- Original title (Japanese)
- ダイナミックPRAに適用可能なソースターム評価手法の開発
Identifiers
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai Wabun Ronbunshi (Online)
- Journal Volume
- 19
- Journal Issue
- 1
- Series
- 雑誌名:日本原子力学会和文論文誌
- Journal Page Range
- p. 34-46
- ISSN
- 2186-2931
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51090908
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CESIUM 137; FAILURE MODE ANALYSIS; FISSION PRODUCT RELEASE; MARKOV PROCESS; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RADIONUCLIDE MIGRATION; REACTOR VESSELS; RISK ASSESSMENT; SEVERE ACCIDENTS; SOURCE TERMS; STATION BLACKOUT
- Descriptors DEC
- ACCIDENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; CESIUM ISOTOPES; CONTAINERS; ENVIRONMENTAL TRANSPORT; INTERMEDIATE MASS NUCLEI; ISOTOPES; MASS TRANSFER; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; POWER PLANTS; RADIOISOTOPES; REACTOR ACCIDENTS; STOCHASTIC PROCESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 12 refs., 10 figs., 3 tabs.