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http://dx.doi.org/10.1016/j.net.2015.01.002

EXPERIMENTAL INVESTIGATIONS RELEVANT FOR HYDROGEN AND FISSION PRODUCT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT  

GUPTA, SANJEEV (Becker Technologies GmbH)
Publication Information
Nuclear Engineering and Technology / v.47, no.1, 2015 , pp. 11-25 More about this Journal
Abstract
The accident at Japan's Fukushima Daiichi nuclear power plant in March 2011, caused by an earthquake and a subsequent tsunami, resulted in a failure of the power systems that are needed to cool the reactors at the plant. The accident progression in the absence of heat removal systems caused Units 1-3 to undergo fuel melting. Containment pressurization and hydrogen explosions ultimately resulted in the escape of radioactivity from reactor containments into the atmosphere and ocean. Problems in containment venting operation, leakage from primary containment boundary to the reactor building, improper functioning of standby gas treatment system (SGTS), unmitigated hydrogen accumulation in the reactor building were identified as some of the reasons those added-up in the severity of the accident. The Fukushima accident not only initiated worldwide demand for installation of adequate control and mitigation measures to minimize the potential source term to the environment but also advocated assessment of the existing mitigation systems performance behavior under a wide range of postulated accident scenarios. The uncertainty in estimating the released fraction of the radionuclides due to the Fukushima accident also underlined the need for comprehensive understanding of fission product behavior as a function of the thermal hydraulic conditions and the type of gaseous, aqueous, and solid materials available for interaction, e.g., gas components, decontamination paint, aerosols, and water pools. In the light of the Fukushima accident, additional experimental needs identified for hydrogen and fission product issues need to be investigated in an integrated and optimized way. Additionally, as more and more passive safety systems, such as passive autocatalytic recombiners and filtered containment venting systems are being retrofitted in current reactors and also planned for future reactors, identified hydrogen and fission product issues will need to be coupled with the operation of passive safety systems in phenomena oriented and coupled effects experiments. In the present paper, potential hydrogen and fission product issues raised by the Fukushima accident are discussed. The discussion focuses on hydrogen and fission product behavior inside nuclear power plant containments under severe accident conditions. The relevant experimental investigations conducted in the technical scale containment THAI (thermal hydraulics, hydrogen, aerosols, and iodine) test facility (9.2 m high, 3.2 m in diameter, and $60m^3$ volume) are discussed in the light of the Fukushima accident.
Keywords
Computational fluid dynamics and lumped-parameter codes; Fission products; Hydrogen; Large-scale experiments; Passive autocatalytic recombiners; Severe accident; THAI test facility;
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  • Reference
1 Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety, The Accident at TEPCO's Fukushima Nuclear Power Stations, Nuclear Emergency Response Headquarters, Government of Japan, 2011.
2 TEPCO, Fukushima Nuclear Accident Analysis Report, June 2012.
3 IAEA, International Fact Finding Expert Mission of the Fukushima Daiichi NPP Accident Following the Great East Japan Earthquake and Tsunami, IAEA mission report, 2011.
4 American Nuclear Society, Fukushima Daiichi: ANS Committee Report, March 2012.
5 SNETP, Final Report of the SNETP Fukushima Task Group on Identification of Research Areas in Response to the Fukushima Accident, 2013.
6 US-NRC, General Electric Advanced Technology Manual, Accession Number ML11259A295, 2011.
7 F. Dehousse, The Nuclear Safety Framework in the European Union after Fukushima, EGMONT Paper 73, Academia Press, 2014.
8 European Nuclear Safety Regulators Group, Stress Tests Performed on European Nuclear Power Plants, Peer Review Report, 2012.
9 Japan Nuclear Technology Institute, Review of Accident at Tokyo Electric Power Company Incorporated's Fukushima Daiichi Nuclear Power Station and Proposed Countermeasures, 2011.
10 Nuclear Regulatory Authority Japan, Outline of New Regulatory Requirements for Light Water Nuclear Power Plants (Severe Accident Measures), 2013.
11 M. Matusuura, K. Hisamochi, S. Ookiod, K. Ando, S. Oda, Efforts to improve safety of nuclear power plant, Hitachi Review 69 (2014) 191e198.
12 J.T. Seo, Post Fukushima Actions in Korea, IAEA-TWG LWR, Vienna, 2013.
13 S. Basu, Technical Basis for Containment Vent Filtration Strategies, EU-PASSAM 1st Workshop on Source Terms Mitigation of Severe Accidents, CIEMAT Headquarters, Madrid, 2014.
14 E. Bachellerie, F. Arnould, M. Auglaire, B. de Boeck, O. Braillard, B. Eckardt, F. Ferroni, R. Moffett, Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments, Nuclear Engineering and Design 221 (2003) 151e165.   DOI
15 European Nuclear Safety Regulators Group, Stress Tests Performed on European Nuclear Power Plants e Country Specific Report for Germany, Peer Review Report, 2012.
16 T. Albiol, L. Cantrel, L. Herranz, E. Riera, S. Guieu, T. Lind, G. Manzini, A. Auvinen, N. Losch, New Studies on Passive and Active Systems Towards Enhanced Severe Accident Source Term Mitigation e The PASSAM Project, Eurosafe conference, 2012.
17 S. Gupta, H. Nowack, B. Schramm, M. Sonnenkalb, Summary of THAI Experimental Research on PAR Behavior and Related Model Development Cooperative Severe Accident Research Program (CSARP) Meeting, Maryland, 2013.
18 G. Poss, M. Sonnenkalb, Recent OECD-THAI2 Results and Future Programs, Cooperative Severe Accident Research Program (CSARP) Meeting, Maryland, 2013.
19 CSNI, Status Report on Filtered Containment Venting, NEA/CSNI/R(2014)7, 2014.
20 S. Gupta, T. Kanzleiter, K. Fischer, G. Poss, Reactor Safety Research Program at THAI Test Facility, Proc. of the 17th Pacific Basin Nuclear Conference, Mexican Nuclear Society, Cancun, 2010.
21 F. Funke, G. Weber, H.-J. Allelein, T. Kanzleiter, W. Morell, G. Poss, Multi-Compartment Iodine Tests in the ThAI Facility, Eurosafe Forum, Berlin, 2004.
22 HySafe, Biennal Report on Hydrogen Safety, Chapter 1: Hydrogen Fundamentals, Version 1, 2007.
23 R.K. Kumar, G.W. Koroll, M. Heitsch, E. Studer, Carbon Monoxide e Hydrogen Combustion Characteristics in Severe Accident Containment Conditions, NEA/CSNI/R 10 (2000), 2000.
24 W. Cronenberg, In-vessel Zircaloy Oxidation/Hydrogen Generation Behavior during Severe Accidents, NUREG/ CR5597, 1990.
25 NRA, Analysis of the TEPCO Fukushima Daiichi NPS Accident, Interim Report by Nuclear Regulatory Authority, Japan, October 2014.
26 U. Bielert, W. Breitung, A. Kotchourko, P. Royl, W. Scholtyssek, A. Veser, A. Beccantini, F. Dabbene, H. Paillere, E. Studer, T. Huld, H. Wilkening, B. Edlinger, C. Poruba, M. Mohaved, Multi-dimensional simulation of hydrogen distribution and turbulent combustion in severe accidents, Nuclear Engineering and Design 209 (2001) 165e172.   DOI
27 M. Ogino, Study on the Issues about Hydrogen Explosion at Fukushima Daiichi NPS, Japan, Nuclear Energy Safety Organization, Technical Workshop on the Accident of TEPCO's Fukushima Daiichi NPS, 2012.
28 T.F. Kanzleiter, Hydrogen deflagration experiments performed in a multi-compartment containment, in: 12th International Conference on Structure Mechanics in Reactor Technology (SMiRT-12), Elsevier Science Publishers, Stuttgart, Germany, 1993, pp. 61e65.
29 T. Kanzleiter, S. Gupta, K. Fischer, G. Ahrens, G. Langer, A. Kuhnel, G. Poss, G. Langrock, F. Funke, Hydrogen and Fission Product Issues Relevant for Containment Safety Assessment under Severe Accident Conditions. OECD-NEA THAI Project Final Report No. 150 1326eFR 1, Becker Technologies GmbH, Eschborn, Germany, June 2010.
30 K. Fischer, T. Kanzleiter, Large Scale Experiments on Gas Distribution in the Containment, Proceedings of the International Topical Meeting on Safety of Nuclear Installations TOPSAFE, Dubrovnik, Croatia, 2008.
31 H.J. Allelein, K. Fischer, J. Vendel, J. Malet, E. Studer, S. Schwarz, M. Houkema, H. Paillere, A. Bentaib, International Standard Problem ISP-47 on Containment Thermal Hydraulics, Report NEA/CSNI/R, 2007.
32 S. Schwarz, K. Fischer, A. Bentaib, J. Burkhard, J.-J. Lee, J. Duspiva, D. Visser, J. Kyttala, P. Royl, J. Kim, P. Kostka, R. Liang, Benchmark on hydrogen distribution in a containment based on the OECD-NEA THAI HM-2 experiment, in: Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2009. NURETH13, Kanazawa city, Japan.
33 Y.H. Koo, Y.S. Yang, K.W. Song, Radioactivity release from the Fukushima accident and its consequences: a review, Progress in Nuclear Energy 74 (2014) 61e70.   DOI
34 M. Freitag, E. Schmidt, S. Gupta, G. Poss, Simulation Benchmark Based on THAI-Experiment on Dissolution of a Steam Stratification by Natural Convection, CFD4NRS-5, OECD-NEA and IAEA workshop, 2014.
35 J.W. Park, B.R. Koh, K.Y. Suh, Testing of honeycomb passive autocatalytic recombiner for nuclear power plant, Nuclear Engineering and Design 241 (2011) 4280e4288.   DOI
36 S. Gupta, T. Kanzleiter, G. Poss, Investigation of hydrogen and fission product issues for containment safety assessment under severe accident conditions: OECD-NEA THAI Project, in: Proceedings of the 45th Annual Meeting on Nuclear Technology, 2014. Frankfurt, Germany.
37 A. Stohl, P. Seibert, G. Wotawa, D. Arnold, F. Burkhart, S. Eckhardt, C. Tapia, A. Vargas, T.J. Yasunari, Xenon-133 and caesium-137 releases into the atmosphere from the Fukushima Dai-ichi nuclear power plant: determination of the source term, atmospheric dispersion, and deposition, Atmospheric Chemistry and Physics 12 (2012) 2313e2343.   DOI
38 J.M. Schwantes, C.R. Orton, R.A. Clark, Analysis of a Nuclear Accident: Fission and Activation Product Release from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel, Pacific Northwest National Laboratory, Report for US-DOE, 2012.
39 CSNI, Pressure Suppression System Containments, A State-Of-The-Art Report by a Group of Experts of the NEA/CSNI, 1986.
40 S. Gupta, B. Balewski, K. Fischer, G. Poss, Experimental Investigations of BWR Pressure Suppression Pool Behaviour under Loss of Coolant Accident Conditions, ICAPP-11, Paper 11389, Nice, France, 2011.
41 H. Bunz, M. Koyro, B. Propheter, W. Schock, M. WagnerAmbs, Resuspension of Fission Products from Sump Water, Final Report EUR 14635 EN, 1992.
42 G. Poss, S. Gupta, M. Sonnenkalb, M. Pelzer, Aerosol Washdown Tests and Information on Actual THAI Activities, Cooperative Severe Accident Research Program (CSARP) Meeting, Maryland, 2011.
43 G. Weber, F. Funke, G. Poss, Iodine Transport and Behaviour in Large Scale THAI Tests. 4th European Review Meeting on Severe Accident Research ERMSAR, ENEA Bologna, 2010.
44 B. Balewski, S. Gupta, K. Fischer, G. Poss, Experimental Investigation of Air Bubble Flows in a Water Pool, NURETH14, Toronto, Canada, paper 036, 2011.
45 CSNI, Physical and Chemical Characteristics of Aerosols in the Containment, Report by a Group of Experts, NEA/CSNI/R(93) 7, 1993.
46 V. Shepelin, D. Koshmanov, E. Chepelin, Catalysts for Hydrogen Removal: Kinetic Paradox and functioning at high concentration of hydrogen, Corsica, France, in: Proceedings of the International Conference on Hydrogen Safety (ICHS 2009), 2009.
47 US-NRC, Consideration of Additional Requirements for Containment Venting Systems for Boiling Water Reactors with MARK I and MARK II Containments, SECY-12-0157, 2012.
48 IAEA, Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants, IAEA TECDOC 1661, 2011.
49 OECD/NEA, State-of-the-art Report on Containment Thermal-hydraulics and Hydrogen Distribution, Nuclear Safety NEA/CSNI/R 16 (1999), 1999.
50 Science Council of Japan, A Review of the Model Comparison of Transportation and Deposition of Radioactive Materials Released to the Environment as a Result of the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Accident Sectional Committee on Nuclear Accident, Committee on Comprehensive Synthetic Engineering, Science Council of Japan, 2014.
51 S. Gupta, G. Poss, M. Sonnenkalb, H. Nowack, Summary of THAI Experimental Basic Research Relevant for Pool Scrubbing and Containment Venting Issues and Related Model Development, Cooperative Severe Accident Research Program (CSARP) Meeting, Maryland, 2014.
52 The Fukushima Nuclear Accident Independent Investigation Commission, The National Diet of Japan, The Official Report of the Fukushima Nuclear Accident Independent Investigation Commission, 2012.
53 OECD/NEA, The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt, NEA no. 7161, 2013.