The objective of this paper is to develop a probabilistic risk assessment (PRA) methodology against volcanic eruption for decay heat removal function of sodium-cooled fast reactors (SFRs). In the volcanic PRA methodology development, only the effect of volcanic tephra (pulverized magma) is taken into account, because there is a great distance between a plant site assumed in this study and volcanoes. The volcanic tephra (ash) could potentially clog air filters of air-intakes that are essential for the decay heat removal. The degree of filter clogging can be calculated by atmospheric concentration of ash and tephra fallout duration and also suction flow rate of each component. This study evaluated a volcanic hazard using a combination of tephra fragment size, layer thickness, and duration. In this paper, functional failure probability of each component is defined as a failure probability of filter replacement obtained by using a grace period to filter failure. Finally, based on an event tree, a core damage frequency has been estimated by multiplying discrete hazard frequencies by conditional decay heat removal failure probabilities. A dominant sequence has been identified as well. In addition, sensitivity analyses have investigated the effects of a tephra arrival reduction factor and prefilter covering.
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September 2018
Research-Article
Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors
Hidemasa Yamano,
Hidemasa Yamano
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: yamano.hidemasa@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: yamano.hidemasa@jaea.go.jp
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Hiroyuki Nishino,
Hiroyuki Nishino
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: nishino.hiroyuki@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: nishino.hiroyuki@jaea.go.jp
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Kenichi Kurisaka,
Kenichi Kurisaka
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: kurisaka.kennichi@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: kurisaka.kennichi@jaea.go.jp
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Takahiro Yamamoto
Takahiro Yamamoto
Geological Survey of Japan,
National Institute of Advanced Industrial Science
and Technology (AIST),
1-1-1 Higashi,
Tsukuba 305-8567, Ibaraki, Japan
e-mail: t-yamamoto@aist.go.jp
National Institute of Advanced Industrial Science
and Technology (AIST),
1-1-1 Higashi,
Tsukuba 305-8567, Ibaraki, Japan
e-mail: t-yamamoto@aist.go.jp
Search for other works by this author on:
Hidemasa Yamano
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: yamano.hidemasa@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: yamano.hidemasa@jaea.go.jp
Hiroyuki Nishino
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: nishino.hiroyuki@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: nishino.hiroyuki@jaea.go.jp
Kenichi Kurisaka
Advanced Fast Reactor Cycle R&D Center,
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: kurisaka.kennichi@jaea.go.jp
Japan Atomic Energy Agency (JAEA),
4002 Narita-cho,
Oarai 311-1393, Ibaraki, Japan
e-mail: kurisaka.kennichi@jaea.go.jp
Takahiro Yamamoto
Geological Survey of Japan,
National Institute of Advanced Industrial Science
and Technology (AIST),
1-1-1 Higashi,
Tsukuba 305-8567, Ibaraki, Japan
e-mail: t-yamamoto@aist.go.jp
National Institute of Advanced Industrial Science
and Technology (AIST),
1-1-1 Higashi,
Tsukuba 305-8567, Ibaraki, Japan
e-mail: t-yamamoto@aist.go.jp
1Corresponding author.
Manuscript received October 28, 2016; final manuscript received April 14, 2017; published online December 5, 2017. Assoc. Editor: Mohammad Pourgol-Mohammad.
ASME J. Risk Uncertainty Part B. Sep 2018, 4(3): 030902 (9 pages)
Published Online: December 5, 2017
Article history
Received:
October 28, 2016
Revised:
April 14, 2017
Citation
Yamano, H., Nishino, H., Kurisaka, K., and Yamamoto, T. (December 5, 2017). "Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors." ASME. ASME J. Risk Uncertainty Part B. September 2018; 4(3): 030902. https://doi.org/10.1115/1.4037877
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