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Journal Articles

Temperature performance of portable radiation survey instruments used for environmental monitoring and clean-up activities in Fukushima

Saegusa, Jun; Yanagisawa, Kayo; Hasumi, Atsushi; Shimizu, Takenori; Uchida, Yoshiaki*

Radiation Physics and Chemistry, 137, p.210 - 215, 2017/08

 Times Cited Count:1 Percentile:10.71(Chemistry, Physical)

Following the Fukushima Daiichi Nuclear Power Plant (NPP) accident, large-scale radiation monitoring and environmental clean-up activities have been conducted throughout the Fukushima region. Outside air temperatures there reach 40$$^{circ}$$C in summer and -20$$^{circ}$$C in winter, which are beyond the quoted range of many radiation survey instruments. For the purpose, temperature performances of four types of portable Japanese survey instruments which are widely used in Fukushima were experimentally investigated with a temperature-controlled chamber.

Journal Articles

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.

Journal Articles

Probabilistic risk assessment method development for high temperature gas-cooled reactors, 3; Development plan of seismic fragility analysis method

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

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 5 Pages, 2017/04

In this paper, an overview of development plan for seismic PRA methodology for high temperature gas-cooled reactors (HTGRs) is discussed focusing on seismic fragility analysis. The developed seismic fragility analysis has the features as follows: (1) Appropriate treatment of uncertainty in seismic fragility analysis, (2) Utilization of ground motion simulation considering fault rupture process, (3) Utilization of detailed finite element models for seismic fragility analysis. It is also intended that seismic fragility analysis method to be developed is applicable to that of light water reactors.

Journal Articles

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.

Oral presentation

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.

Oral presentation

Estimation of inhomogeneous attenuation structure using multi-step spectral inversion method

Takada, Tsuyoshi; Imazeki, Suguru*; Itoi, Tatsuya*; Hida, Takenori*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Applicability of extended correlation anomaly detection to intra-structure performance monitoring

Takada, Tsuyoshi; Yaoyama, Taro*; Hida, Takenori*

no journal, , 

no abstracts in English

Oral presentation

Development of nonlinear seismic response analysis model of human body considering individual differences

Takada, Tsuyoshi; Matsumoto, Yuma*; Hida, Takenori*; Itoi, Tatsuya*

no journal, , 

no abstracts in English

Oral presentation

Consideration of evacuation planning of urban area for tsunami with short arrival time using agent-based simulation

Takada, Tsuyoshi; Minamihara, Akira*; Hida, Takenori*; Itoi, Tatsuya*

no journal, , 

no abstracts in English

Oral presentation

A Study on the way to keep standing for evaluation of possibility of overturning of human body during earthquake based on shaking table test

Takada, Tsuyoshi; Muraji, Toru*; Matsumoto, Yuma*; Hida, Takenori*; Itoi, Tatsuya*

no journal, , 

no abstracts in English

Oral presentation

Development and application of seismic fragility analysis method for high temperature gas-cooled reactors

Nishida, Akemi; Itoi, Tatsuya*; Takada, Tsuyoshi*; Hida, Takenori*; Muramatsu, Ken*; 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. In this presentation, an overview of development for seismic PRA methodology for high temperature gas-cooled reactors (HTGRs) is explained focusing on seismic fragility analysis. The developed seismic fragility analysis has the features as follows: (1) Appropriate treatment of uncertainty in seismic fragility analysis, (2) Utilization of ground motion simulation considering fault rupture process, (3) Utilization of detailed finite element models for seismic fragility analysis. It is also intended that seismic fragility analysis method to be developed is applicable to that of light water reactors.

Oral presentation

Development of seismic response analysis model of nuclear facility based on strong motion records and 4SID

Kato, Rino*; Hida, Takenori*; Tsutsumi, Hideaki*; Takada, Tsuyoshi

no journal, , 

With the aim of constructing a more realistic earthquake response analysis model of a nuclear facility, we constructed a model using the system identification method developed by the authors making maximum use of the strong motion observation records in the past earthquakes, and discussed its validity.

13 (Records 1-13 displayed on this page)
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