[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.1016/j.net.2014.12.011

EVALUATION OF PLANT OPERATIONAL STATES WITH THE CONSIDERATION OF LOOP STRUCTURES UNDER ACCIDENT CONDITIONS

MATSUOKA, TAKESHI (College of Nuclear Science and Technology, Harbin Engineering University)

Publication Information

Nuclear Engineering and Technology / v.47, no.2, 2015 , pp. 157-164 More about this Journal

Abstract

Nuclear power plants have logical loop structures in their system configuration. This paper explains the method to solve a loop structure in reliability analysis. As examples of loop structured systems, the reactor core isolation cooling system and high-pressure core injection system of a boiling water reactor are considered and analyzed under a station blackout accident condition. The analysis results show the important role of loop structures under severe accidents. For the evaluation of the safety of nuclear power plants, it is necessary to accurately evaluate a loop structure's reliability.

Keywords

Fukushima Daiichi; High-pressure core injection system; Loop structure; Nuclear power plant; Reactor core isolation cooling system; Reliability; Safety;

Citations & Related Records

Reference

1	T. Matsuoka, An exact method for solving logical loops in reliability analysis, Rel. Eng. Sys. Saf. 94 (2009) 1282-1288. DOI
2	T. Matsuoka, Generalized method for solving logical loops in reliability analysis, in: Proceedings of PSAM-11, Helsinki, Finland, 2012.
3	G.A. Coles, T.B. Powers, Breaking the logic loop to complete the probabilistic risk assessment, in: Proceeding of PSA'89, Pittsburgh, 1989, pp. 1155-1160.
4	T. Matsuoka, A method to solve logical loops in the GO-FLOW Methodology, in: Proceedings of PSAM-V, Osaka, 2000, pp. 1461-1465.
5	J.K. Vaurio, A recursive method for breaking complex logic loops in Boolean system models, Rel. Eng. Sys. Saf. 92 (2007) 1473-1475. DOI
6	T. Matsuoka, Method for solving logical loops in system reliability analysis, Int. J. Nucl. Saf. Simul. 1 (2010) 328-339.
7	S. Even, Sequential Boolean Equations, Appendix; Solution of Boolean Equations, IEEE Trans. Comput. C-18 (1969) 230-240.
8	Prime minister of Japan and his cabinet, Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety - The Accident at TEPCO's Fukushima Nuclear Power Stations, 2011.
9	Japan atomic energy society, A Standard for Procedures of Probabilistic Safety Assessment of Nuclear Power Plants during Power Operation 2008 (Level 1 PSA), AESJ-SC-P008, 2008.
10	T. Matsuoka, GO-FLOW methodology - Basic concept and integrated analysis framework for its applications, Int. J. Nucl. Saf. Simul. 1 (2010) 198-206.
11	T. Matsuoka, M. Kobayashi, GO-FLOW: a new reliability analysis methodology, Nucl. Sci. Eng. 98 (1998) 64-78.
12	IAEA, Survey of Ranges of Component Reliability Data for Use in Probabilistic Safety Assessment, IAEA-TECDOC-508, 1989.
13	J.E. Yang, S.H. Han, J.H. Park, Y.H. Jin, Analytic method to break logical loops automatically in PSA, Rel. Eng. Sys. Saf. 56 (1997) 101-105. DOI