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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.

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

JAEA Reports

Seismic study on high temperature gas-cooled reactor core

JAERI 1322, 157 Pages, 1991/04

JAERI-1322.pdf:5.34MB

no abstracts in English

Journal Articles

Journal Articles

Seismic response of high temperature gas-cooled reactor core with block-type fuel, IV; Seismic reaponse of actual core predicted from experimental and analytical results of two-dimensional core modela

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Nihon Genshiryoku Gakkai-Shi, 27(2), p.145 - 158, 1985/00

 Times Cited Count:2 Percentile:37.09(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Two-Dimenional Vertical model Seismic Test and Analysys for HTGR Core

;

JAERI 1282, 68 Pages, 1983/02

JAERI-1282.pdf:3.43MB

no abstracts in English

JAEA Reports

Journal Articles

Seismic research on block-type HTGR core

; ;

Nucl.Eng.Des., 71, p.195 - 215, 1982/00

 Times Cited Count:9 Percentile:68.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Seismic response of high temperature gas-cooled reactor core with block-type fuel,III; Vibration experiment of two-dimensional vertical slice core model

;

Journal of Nuclear Science and Technology, 18(7), p.514 - 524, 1981/00

 Times Cited Count:4 Percentile:52.22(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JAEA Reports

One-Region Core ModelSeimic Test and Analysis for HTGR Core

;

JAERI-M 9199, 61 Pages, 1980/11

JAERI-M-9199.pdf:3.81MB

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

GTOROTO:A Simulation System for HTGR Core Seismic Behavior

; ;

JAERI-M 8937, 44 Pages, 1980/07

JAERI-M-8937.pdf:2.04MB

no abstracts in English

Journal Articles

Seismic response of high temperature gas-cooled reactor core with block-type fuel, 1; Stacked colum vibration experiment

; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 22(1), p.55 - 67, 1980/00

 Times Cited Count:4 Percentile:48.70(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Seismic Response Analysis for Prismatic Fuel HTGR Core

JAERI-M 8273, 38 Pages, 1979/06

JAERI-M-8273.pdf:0.76MB

no abstracts in English

28 (Records 1-20 displayed on this page)