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Matsuda, Kosuke*; Muramatsu, Ken*; Muta, Hitoshi*; Sato, Hiroyuki; Nishida, Akemi; Ohashi, Hirofumi; Itoi, Tatsuya*; Takada, Tsuyoshi*; Hida, Takenori*; Tanabe, Masayuki*; et al.
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04
This paper proposes a set of procedures for accident sequence analysis in seismic PRAs of HTGRs that can consider the unique accident progression characteristics of HTGRs. Main features of our proposed procedure are as follows: (1) Systematic analysis techniques including Master Logic Diagrams are used to ensure reasonable completeness in identification of initiating events and classification of accident sequences, (2) Information on factors that govern the accident progression and source terms are effectively reflected to the construction of event trees for delineation of accident sequences, and (3) Frequency quantification of seismically-initiated accident sequence frequencies that involve multiplepipe ruptures are made with the use of the Direct Quantification of Fault Trees by Monte Carlo (DQFM) method by a computer code SECOM-DQFM.
Muramatsu, Ken*; Muta, Hitoshi*; Matsuda, Kosuke*; Sato, Hiroyuki; Nishida, Akemi; Ohashi, Hirofumi; Itoi, Tatsuya*; Tanabe, Masayuki*
no journal, ,
As part of PRA method development for High temperature Gas-cooled Reactor, domestic and international PRA standards are investigated to identify requirements related to accident scenario assessment and reliability database development. It was concluded that there are three key thing to note for the PRA method development, that is, detail analysis for passive components, integration of mechanistic source term evaluation and supplementation of reliability data.
Matsuda, Kosuke*; Muramatsu, Ken*; Muta, Hitoshi*; Sato, Hiroyuki; Nishida, Akemi; Itoi, Tatsuya*
no journal, ,
The selection of initiating model for seismic PRA is studied. System analysis are conducted and compared for the case with initiating event hierarchy tree and the case with a multiple branching event tree. The analysis is performed with SECOM2-DQFM code developed by Japan Atomic Energy Agency. As a result of study, we have found the effective classification method for the seismic initiating events with satisfactory accuracy.
Matsuda, Kosuke*; Muta, Hitoshi*; Muramatsu, Ken*; Otori, Yasuki*; Sato, Hiroyuki; Nishida, Akemi; Itoi, Tatsuya*
no journal, ,
Towards the establishment of evaluation method for accident sequences initiated by seismic, applicability of system reliability analysis code SECOM2-DQFM-U for the sequence is evaluated.
Matsuda, Kosuke*; Muta, Hitoshi*; Muramatsu, Ken*; Oshima, Haruki*; Sato, Hiroyuki
no journal, ,
The presentation will cover achievements of accident sequence evaluation method development which can adequately treat occurrence probability of failure in structures and static components with the consideration of correlation of those failures aiming to establish a probabilistic risk assessment method considering safety and design features of high temperature gas-cooled reactors.
Sato, Hiroyuki; Nishida, Akemi; Ohashi, Hirofumi; Muramatsu, Ken*; Muta, Hitoshi*; Matsuda, Kosuke*; Itoi, Tatsuya*; Takada, Tsuyoshi; Tanabe, Masayuki*; Yamamoto, Tsuyoshi*; et al.
no journal, ,