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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, 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.

Journal Articles

Development of a hazard curve evaluation method for a forest fire as an external hazard

Okano, Yasushi; Yamano, Hidemasa

Proceedings of International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2015) (USB Flash Drive), p.22 - 31, 2015/04

An external hazard curve of a forest fire is evaluated based on a logic tree. The logic tree consists domains of "forest fire breakout and spread conditions", "weather condition" and "vegetation and topographical conditions". A location nearby a typical nuclear power plant site in Japan was selected, and the frequency of a large forest fire of the location is approximately 1/5 of the average in Japan. Forest fire breakout points were selected considering typical forest fire causes in Japan. The weather conditions are represented by two parameter sets of "temperature-humidity" and "wind direction-wind speed". A number of forest fire simulations were performed to obtain a response surface for a frontal fireline intensity. The hazard curve is therefore evaluated by a Monte Carlo simulation such that the annual exceedance probability is about 1.0$$times$$10$$^{-4}$$ per year for the frontal fireline intensity of 200 kW/m and about 1.3$$times$$10$$^{-5}$$ per year for 300 kW/m.

JAEA Reports

None

; *; *

JNC-TN8200 2001-001, 42 Pages, 2001/01

JNC-TN8200-2001-001.pdf:3.16MB

None

JAEA Reports

None

JNC-TN1400 2001-002, 172 Pages, 2001/01

JNC-TN1400-2001-002.pdf:6.28MB

no abstracts in English

JAEA Reports

Improvement of DYANA ; The dynamic analysis program for event transition

*; *

JNC-TJ9440 2000-004, 22 Pages, 2000/03

JNC-TJ9440-2000-004.pdf:2.35MB

In the probabilistic safety assessment(PSA), the fault tree/event tree technique has been widely used to evaluate accident sequence frequencies. However, event tansition which operators actually face can not be dynamically treated by the conventional technique. Therefore, we have made the dynamic analysis program(DYANA) for event transition for a liquid metal cooled fast breeder reactor. In the previous development, we made basic model for analysis. However, we have a probrem that calculation time is too long. At the current term, we made parallelization of DYANA usig MPI. So we got good performance on WS claster. It performance is close to ideal one.

JAEA Reports

Analyses of transient plant response under emergency situations (2)

*; *

JNC-TJ9440 2000-002, 90 Pages, 2000/03

JNC-TJ9440-2000-002.pdf:1.43MB

In order to support development of the dynamic reliability analysis program DYANA, analyses were made on the event sequences anticipated under emergency situations using the plant dynamics simulation computer code Super-COPD. In this work 9 sequences were analyzed and integrated into an input file for preparing the functions for DYANA using the analytical model and input data which developed for Super-COPD in the previous work. These sequences could not analyze in the previous work, which were categorized into the PLOHS (Protected Loss of Heat Sink) event.

JAEA Reports

Improvement of biosphere model for performance assessment of geological disposal system (III)

Ikeda, Takao*; Yoshida, Hideji*; *

JNC-TJ8400 2000-046, 264 Pages, 2000/02

JNC-TJ8400-2000-046.pdf:6.73MB

This report contains discussions about methodology for the selection of parameter values, stochastic approach for the biosphere assessment and biosphere modelling for marine discharge case are described. Regarding the methodology for the selection of parameter values, important aspects for the data selection were discussed, and data selection protocol was developed. Regarding the stochastic approach for the biosphere assessment, it is confirmed that Straightforward Monte Carlo Method and Latin Hypercube Sampling Method are the most adequate based on a literature survey. Then stochastic assessment by using biosphere model that was developed in the second progress report was carried out to check the sensitivity of parameter values. Finally, availability of several kind of assessment models for marine discharge case were discussed. It was confirmed that Multiple Compartment Model was the most applicable. Assessment using Multiple Compartment Model was carried out. The results were compared with those derived by numerical model. As a result, the difference between two models were small enough.

JAEA Reports

None

Ikeda, Takao*; Yoshida, Hideji*; *

JNC-TJ8400 2000-045, 134 Pages, 2000/02

JNC-TJ8400-2000-045.pdf:4.12MB

None

JAEA Reports

Refinement of a system Configration control program (II); Development of the database function for cutsets of accident sequences and enhancement of GUI

*; *; *

JNC-TJ9440 2000-003, 173 Pages, 1999/03

JNC-TJ9440-2000-003.pdf:19.86MB

In FY 1997, a program which evaluates the risk in each phase of the maintenance was developed to support the maintenance planning on an FBR plant. In FY 1998, the GUI (Graphical User Interface) of the program developed in FY 1997 was enhanced for its user-friendlyness including facilitation of data settings and interpretation of the computational results. Specifically, following functions were incorporated : (1)To call associated window displays (editing and reporting display) mutually. (2)To edit the combinations of the systems for their maintenance scheduling. Furthermore, some risk evaluation functions such as the database function for cutsets of accident sequences and tracking function of risk trends were developed and added to its analysis module. A series of test on the programs with the GUI and the analysis module was performed and it was verified that the progam worked correctly.

JAEA Reports

None

*

PNC-TJ1222 98-002, 70 Pages, 1998/02

PNC-TJ1222-98-002.pdf:2.33MB

None

JAEA Reports

None

*

PNC-TJ1222 98-001, 212 Pages, 1998/02

PNC-TJ1222-98-001.pdf:20.18MB

None

JAEA Reports

None

PNC-TN1410 97-043, 167 Pages, 1997/11

PNC-TN1410-97-043.pdf:7.22MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-034, 338 Pages, 1997/09

PNC-TN1410-97-034.pdf:6.65MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-014, 87 Pages, 1997/03

PNC-TN1410-97-014.pdf:2.92MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-010, 462 Pages, 1997/02

PNC-TN1410-97-010.pdf:17.56MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-009, 345 Pages, 1997/02

PNC-TN1410-97-009.pdf:13.42MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 96-078, 581 Pages, 1996/12

PNC-TN1410-96-078.pdf:21.02MB

no abstracts in English

JAEA Reports

None

PNC-TN1010 96-001, 59 Pages, 1996/03

PNC-TN1010-96-001.pdf:2.32MB

no abstracts in English

JAEA Reports

None

*

PNC-TJ1222 96-005, 66 Pages, 1996/03

PNC-TJ1222-96-005.pdf:1.33MB

None

44 (Records 1-20 displayed on this page)