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http://dx.doi.org/10.5516/NET.03.2013.079

SEVERE ACCIDENT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT AND IMPROVEMENTS SUGGESTED  

Song, Jin Ho (Korea Atomic Energy Research Institute)
Kim, Tae Woon (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.46, no.2, 2014 , pp. 207-216 More about this Journal
Abstract
This paper revisits the Fukushima accident to draw lessons in the aspect of nuclear safety considering the fact that the Fukushima accident resulted in core damage for three nuclear power plants simultaneously and that there is a high possibility of a failure of the integrity of reactor vessel and primary containment vessel. A brief review on the accident progression at Fukushima nuclear power plants is discussed to highlight the nature and characteristic of the event. As the severe accident management measures at the Fukushima Daiich nuclear power plants seem to be not fully effective, limitations of current severe accident management strategy are discussed to identify the areas for the potential improvements including core cooling strategy, containment venting, hydrogen control, depressurization of primary system, and proper indication of event progression. The gap between the Fukushima accident event progression and current understanding of severe accident phenomenology including the core damage, reactor vessel failure, containment failure, and hydrogen explosion are discussed. Adequacy of current safety goals are also discussed in view of the socio-economic impact of the Fukushima accident. As a conclusion, it is suggested that an investigation on a coherent integrated safety principle for the severe accident and development of innovative mitigation features is necessary for robust and resilient nuclear power system.
Keywords
Fukushima Accident; Severe Accident; Severe Accident Management; Severe Accident Phenomenology; Boling Water Reactor;
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1 J. L. Rempe, S. A. Chaez, G. L. Thinne, C. M. Allison, G. E. Korth, R. J. Witt, J. J. Sienicki , S. K. Wang, L. A. Stickler, C. H. Heath, S. D. Snow, NUREG/CR-5642, EGG-2618, Light Water Reactor Lower Head Failure Analysis, 1993.
2 L. A. Stickler, J. L. Rempe, S.A. CMvez, G. L. Thinnes, S. D. Snow, R. J. Witt, M. L. Corradini, J. A. Kos, NUREG/CR-6196, TMI V(93)EG01, EGG-2733, Calculations to Estimate the Margin to Failure in the TMI-2 Vessel, 1994.
3 S.A. Hodge, BWR Reactor Vessel Bottom Head Failure Modes, Dubmvnik, Yugoslavia, CONF-89, 546-3, December 1989.
4 Haruo Fujimoto, Keisuke Kondo, Tomomichi Ito, Yusuke Kasagawa, Osamu Kawabata, Masao Ogino and Masahiro Yamashita, Circumstances and Present Situation of Accident Management Implementation in Japan, OECD/NEA Workshop on Implementation of Severe Accident Management Measures (ISAMM-2009), Bottstein, Switzerland, October 26-28, 2009
5 S. A. Hodge. J. C. Cleveland, T. S. Kress, M. Petck, Identification and Assessment of BWR In-Vessel Severe Accident Mitigation Strategies, NUREG/CR-5869, ORNL/TM-12080, 1992.
6 Juan J. Carbajo, MELCOR sensitivity studies for a lowpressure short-term station blackout at the Peach Bottom plant, Nuclear Engineering and Design 152 (1994) 287-317   DOI   ScienceOn
7 R.J. Park, S.W. Hong, "Effect of SAMG entry condition on operator action time for severe accident mitigation", Nuclear Engineering and Design, Vol. 241, pp. 1807-1812, 2011   DOI   ScienceOn
8 http://www.tepco.co.jp/en/nu/fukushima-np/water/images/130826_02.pdf
9 R. O. Gaunt et. al, Fukushima Daiichi Accident Study, SAND2012-6173, August 2012
10 YVL 2.2, Transient and accident analyses for justification of technical solutions at nuclear power plants, 26 August 2003
11 R. D. Mosteller, F. J. Rahnf, Monte Carlo calculations for recriticality during the reflood phase of a severe accident in a boiling water reactor, Nuclear technology, 1995, vol. 110, no2, pp. 168-180.   DOI
12 T. Hakada and D. Johnson, Defining Societal Safety Goals on Environment Protection for Nuclear Power Plants, PSAM 2013, Tokyo, 2013
13 Dennis Bley, Stan Kaplan & David Johnson, The strengths and limitations of PSA: where we stand, Reliability Engineering and System Safety 38 (1992) 3-26   DOI   ScienceOn
14 IAEA Specific Safety Requirements NO. SSR-2/1, "Safety of Nuclear Power Plants: Design", 2012
15 EA-12-051, NRC Order on Spent Fuel Pool Instrumentation, March 12, 2012, USNRC
16 Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety - The Accident at TEPCO's Fukushima Nuclear Power Stations -, June 2011, Nuclear Emergency Response Headquarters, Government of Japan
17 Fukushima Nuclear Accident Analysis Report, Tokyo Electric Power Company, Inc., June 20, 2012 1.
18 INPO 11-005, Special report on the nuclear accident at the Fukushima Daiichi Nuclear Power Station, November 2011.
19 IAEA Safety Standard Series, Safety Standards Series No. NS-G-1.5, External Events excluding earthquakes in the Design of Nuclear Power Plants, 2003.
20 N. Taleb, The Black Swan - The Impact of Highly Improbable, Random house, 2007.
21 C.D. Fletcher, R.M. Beaton, V. V. Palazov, and D.L. Caraher, SCDAP/RELAP5 Thermal-Hydraulic Evaluations of the Potential for Containment Bypass During Extended Station Blackout Severe Accident Sequences in a Westinghouse Four-Loop PWR, NUREG/CR-6995, 2010.
22 M. Naitoh et. al., Analysis of the Fukushima Daiichi Nuclear Accident by Severe Accident Analysis Code SAMPSON, ERMSAR-2013, Avignon, France, 2-4 October, 2013.
23 M. Naitoh, Facts and Analyses of Fukushima Disaster, and Their Reflections, Prepared for KNS Fall Conference, October, 2011 1.