Unusual redox behavior of ruthenocene confined in the micropores of activated carbon

Itoi, Hiroyuki*; Ninomiya, Takeru*; Hasegawa, Hideyuki*; Maki, Shintaro*; Sakakibara, Akihiro*; Suzuki, Ryutaro*; Kasai, Yuto*; Iwata, Hiroyuki*; Matsumura, Daiju; Owada, Mao*; et al.

Journal of Physical Chemistry C, 124(28), p.15205 - 15215, 2020/07

https://doi.org/10.1021/acs.jpcc.0c02965

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 1; Project overviews

Sato, Hiroyuki; Nishida, Akemi; Ohashi, Hirofumi; Muramatsu, Ken*; Muta, Hitoshi*; Itoi, Tatsuya*; Takada, Tsuyoshi*; Hida, Takenori*; Tanabe, Masayuki*; Yamamoto, Tsuyoshi*; et al.

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04

JAEA, in conjunction with Tokyo City University, The University of Tokyo and JGC Corporation, have started development of a PRA method considering the safety and design features of HTGR. The primary objective of the project is to develop a seismic PRA method which enables to provide a reasonably complete identification of accident scenario including a loss of safety function in passive system, structure and components. In addition, we aim to develop a basis for guidance to implement the PRA. This paper provides the overview of the activities including development of a system analysis method for multiple failures, a component failure data using the operation and maintenance experience in the HTTR, seismic fragility evaluation method, and mechanistic source term evaluation method considering failures in core graphite components and reactor building.

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 2; Development of accident sequence analysis methodology

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.

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 2; Development of source term evaluation method

Honda, Yuki; Sato, Hiroyuki; Ohashi, Hirofumi; Nishida, Akemi; Muta, Hitoshi*; Muramatsu, Ken*; Itoi, Tatsuya*; Tanabe, Masayuki*

no journal, , 

We have been conducting a source term evaluation method development for high temperature gas-cooled reactors considering structural failures in the major components. We will present the outline of evaluation method and results of transient analysis for unprotected depressurized loss-of-forced cooling accident which may be initiated by Beyond-Design-Basis Earthquake.

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 3; Project overview and progress

Sato, Hiroyuki; Nishida, Akemi; Muramatsu, Ken*; Muta, Hitoshi*; Itoi, Tatsuya*; Takada, Tsuyoshi*; Tanabe, Masayuki*; Yamamoto, Tsuyoshi*

no journal, , 

Japan Atomic Energy Agency, in conjunction with Tokyo City University, The University of Tokyo and JGC Corporation, have started development of a probabilistic risk assessment method considering the safety and design features of High Temperature Gas-cooled Reactor (HTGR). The presentation will focus on project overview and progress in FY2017 and FY2018.

Probabilistic risk assessment method development for High Temperature Gas-cooled Reactors (HTGRs), 9; Consideration on applicability of SECOM 2-DQFM-U code in case of pipe breach accident by seismic

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.

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 12; Development and application of seismic fragility analysis method

Itoi, Tatsuya*; Nishida, Akemi; Takada, Tsuyoshi*; Hida, Takenori*; Sato, Hiroyuki

no journal, , 

This research aims to establish a probabilistic risk assessment method for high temperature gas-cooled reactors fully utilizing their design and safety characteristics. The presentation will explain achievements in the development of fragility analysis method.

Seismic probabilistic risk assessment method development for 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, ,