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research-article

Development of Probabilistic Risk Assessment Methodology against Volcanic Eruption for Sodium-Cooled Fast Reactors

[+] Author and Article Information
Hidemasa Yamano

Advanced Fast Reactor Cycle R&D Center, Japan Atomic Energy Agency (JAEA), 4002 Narita-cho, Oarai, Ibaraki, 311-1393, Japan
yamano.hidemasa@jaea.go.jp

Hiroyuki Nishino

Advanced Fast Reactor Cycle R&D Center, Japan Atomic Energy Agency (JAEA), 4002 Narita-cho, Oarai, Ibaraki, 311-1393, Japan
nishino.hiroyuki@jaea.go.jp

Kenichi Kurisaka

Advanced Fast Reactor Cycle R&D Center, Japan Atomic Energy Agency (JAEA), 4002 Narita-cho, Oarai, Ibaraki, 311-1393, Japan
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, Ibaraki, 305-8567, Japan
t-yamamoto@aist.go.jp

1Corresponding author.

ASME doi:10.1115/1.4037877 History: Received October 28, 2016; Revised April 14, 2017

Abstract

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. 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 pre-filter covering.

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