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Journal Articles

Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors

Nishino, Hiroyuki; Yamano, Hidemasa; Kurisaka, Kenichi

Mechanical Engineering Journal (Internet), 5(4), p.18-00079_1 - 18-00079_17, 2018/08

Journal Articles

Quantitative risk trends deriving from PSA-based event analyses; Analysis of results from U.S.NRC's accident sequence precursor program

Watanabe, Norio

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.396 - 406, 2004/12

The U. S. Nuclear Regulatory Commission has been carrying out the Accident Sequence Precursor (ASP) Program to identify and categorize precursors to potential severe core damage accident sequences using the PSA technique. The ASP Program has identified a lot of risk significant events as precursors that occurred at U. S. nuclear power plants. The results from the ASP Program include valuable information that could be useful for obtaining risk significant insights and for monitoring risk trends in nuclear power industry. The present study examines and discusses quantitative risk trends for the industry level, using two indicators, that is, the occurrence frequency of precursors and the annual core damage probability, deriving from the ASP analysis results. It is shown that the core damage risk at U.S. nuclear power plants has been lowered and the likelihood of risk significant events has been remarkably decreasing. Also, the present study demonstrates that two risk indicators used here can provide quantitative information useful for monitoring risk trends in nuclear power industry.

JAEA Reports

User's manual of SECOM2: A Computer code for seismic system reliability analysis

Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Watanabe, Yuichi*; Tamura, Kazuo*

JAERI-Data/Code 2002-011, 205 Pages, 2002/03

JAERI-Data-Code-2002-011.pdf:8.52MB

This report is a user's manual of seismic system reliability analysis code SECOM2 developed at the JAERI for system reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as calculation of component and system failure probabilities for given seismic motion levels at the site of an NPP based on the response factor method, calculation of accident sequence frequencies and the core damage frequency (CDF), importance analysis using various indicators, uncertainty analysis, and calculation of the CDF taking into account the effect of the correlations of responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about responses and capacities of the components which compose the FT, and seismic hazard curve for the NPP site as input. This report presents calculation method used in the SECOM2 code and how to use those functions in the SECOM2 code.

JAEA Reports

Study for improvement of performance of the test and research reactors

JAERI-Research 99-016, 84 Pages, 1999/03

JAERI-Research-99-016.pdf:2.97MB

no abstracts in English

Journal Articles

Findings from CSARP; Cooperative severe accident research program

Sugimoto, Jun; Hashimoto, Kazuichiro*; Yamano, Norihiro; Hidaka, Akihide; Maruyama, Yu; Uetsuka, Hiroshi; Fuketa, Toyoshi; Nakamura, Takehiko; Soda, Kunihisa; Katanishi, Shoji*

Nihon Genshiryoku Gakkai-Shi, 39(2), p.123 - 134, 1997/02

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of PSA methodology to design improvement of JAERI passive safety reactor (JPSR)

Iwamura, Takamichi; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.316 - 326, 1996/04

 Times Cited Count:1 Percentile:14.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Seismic probabilistic safety assessment methodology development and application to a model plant

Sobajima, Makoto; ; Kondo, Masaaki; *; Muramatsu, Ken;

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.629 - 636, 1996/00

no abstracts in English

Journal Articles

Thermal-hydraulics of LWR severe accident

Sugimoto, Jun

Dennetsu Kenkyu, 34(133), p.52 - 59, 1995/04

no abstracts in English

JAEA Reports

Out-pile FP Release Experiment by Heating of Irradiated UO$$_{2}$$ Pellet

;

JAERI-M 85-199, 16 Pages, 1985/12

JAERI-M-85-199.pdf:0.68MB

no abstracts in English

JAEA Reports

Present Status and Needs of Research on Sever Core Damege

; ; Murao, Yoshio; ; ; ; ; ; ; Ueda, Shuzo; et al.

JAERI-M 82-039, 201 Pages, 1982/05

JAERI-M-82-039.pdf:6.73MB

no abstracts in English

Journal Articles

Post-facta analysis of the TMI accident, II; Analysis of fuel rod behavior or core damage estimation by use of the TOODEE2-J

; ; ; Shimooke, Takanori

Nucl.Eng.Des., 69(1), p.37 - 42, 1982/00

 Times Cited Count:2 Percentile:32.87(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Technical issues for safety improvement, 1; Core damage prevention in case of accidents

Nishi, Yoshihisa*; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Yamada, Hidetomo*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Post-test analysis of the CMMR-4 test bundle

Madokoro, Hiroshi; Yamashita, Takuya; Sato, Ikken

no journal, , 

Oral presentation

Physical characteristics of Shionohira fault damage zone and kuruma fault damage zone based on laboratory tests

Nishiwaki, Takafumi*; Ogawa, Koji*; Aoki, Kazuhiro; Yoshida, Takumi

no journal, , 

Various physical and mechanical tests were performed on shallow borehole cores ($$sim$$ 30 m) taken from the activated Shionohira and the non-activated Kuruma faults associated with the April 2011 Fukushima-ken Hamadori earthquake. The results showed (1) low strength constants and elastic constants for the fault damage zone samples compared to the host rocks; (2) different physical properties for fault gouge, fault breccia, and Cataclasite of the fault damage zone; and (3) for fault gouge, the importance of considering the stress factor on the fault plane. Data accumulation from various fault damage zones is needed to gain better understanding of the physical properties of the fault damage zone.

17 (Records 1-17 displayed on this page)
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