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The Fukushima Event: The Outline and the Technological Background

DOI: 10.1155/2012/507921

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Abstract:

The paper deals with the evaluation of the Fukushima-Daiichi Nuclear Power Plant (NPP) accident in Units 1 to 4: an attempt is made to discuss the scenario within a technological framework, considering precursory documented regulations and predictable system performance. An outline is given at first of the NPP layout and of the sequence of major events. Then, plausible time evolutions of relevant quantities in the different Units, is inferred based on results from the application of numerical codes. Scenarios happening in the primary circuit and containment (three Units involved) are distinguished from scenarios in spent fuel pool (four Units involved). Radiological releases to the environment and doses are approximately estimated. The event is originated by a natural catastrophe with almost simultaneous occurrence of earthquake and tsunami. These caused heavy destruction in a region in Japan much wider than the land around the NPP which was affected by the nuclear contamination. Key outcome from the work is the demonstration of strength for nuclear technology; looking at the past, misleading Probabilistic Safety Assessment (PSA) data and inadequacy in licensing processes have been found. Looking into the future keywords are Emergency Rescue Team (ERT), Enhanced Human Performance (EHP), and Robotics in Nuclear Safety and Security (RNSS). 1. Introduction On March 11, 2011 a magnitude 9.0 (Richter scale) destructive earthquake occurred in the north-east coast of Japan, close to the city of Sendai. The earthquake was followed by an equally devastating tsunami with waves as high as six meters entering a few miles into the land. Thousands of square kilometers of territory were affected, a few percent of the Japan islands surface. Whatever man-made installation like roads, factories, buildings, and dams was destroyed or severely damaged. The death toll accounted for around 30 thousands, that is, more than 2/10000 of the Japanese population. Several Nuclear Power Plants (NPPs) for the electricity production were (and are) in the affected area, including Onagawa (3 Units), Tokai-2 (1 Unit), Fukushima Daiichi (6 Units), and Fukushima Daini (4 Units). At a larger distance, there are the Kashiwazaki Kariwa (7 Units) and the Tohoku (1 Unit) NPPs. All Nuclear Power Plants safely responded to the earthquake and to the tsunami (where concerned) solicitations, including the NPP closest to the epicenter that is, Onagawa, with the noticeable exception of four over six Units of the Fukushima Daiichi installation. Namely, the nuclear accidents in the Units 1 to 4 of

References

[1]  M. Schneider, A. Froggatt, and S. Thomas, “Nuclear power in a post-fukushima world—25 years after the Chernobyl accident,” World Nuclear Industry Status Report, Worldwatch Institute, Washington, DC, USA, 2011.
[2]  V. L. Sailor, K. R. Perkins, J. R. Weeks, and H. R. Connell, “Severe accident in spent fuel pools in support of generic safety issue 82,” Tech. Rep. NUREG/CR-4982, BNL-NUREG-52093, US NRC, Washington, DC, USA, 1987.
[3]  R. Jack Dallman, W. J. Galyean, and K. C. Wagner, “Containment venting as an accident management strategy for BWRS with Mark I containments,” Nuclear Engineering and Design, vol. 121, no. 3, pp. 421–429, 1990.
[4]  M. Lee and G. D. Lee, “Quantification of severe accidents source terms of BWR 4 reactor with Mark I containment using source term code package,” Nuclear Engineering and Design, vol. 138, no. 3, pp. 313–337, 1992.
[5]  I. K. Madni, “Analysis of long term station blackout without automatic depressurization at peach bottom using melcor (version 1.8),” Tech. Rep. NUREG/CR-5850, BNL-NUREG 52319, US NRC, Washington, DC, USA, 1994.
[6]  M. T. Leonard, R. O. Gauntt, and D. A. Power, “Accident source terms for boiling water reactors with high burn-up cores calculated using melcor 1.8.5,” Sandia Report SAND2007-7697, Sandia National Labs, New Mexico, USA, 2007.
[7]  IAEA, Fundamental Safety Principles, SF-1, IAEA, Vienna, Austria, 2006.
[8]  IAEA, Safety of Nuclear Power Plants: Design, NS-R-1, IAEA, Vienna, Austria, 2000.
[9]  IAEA, Safety Requirements: Safety Assessment for Facilities and Activities, GS-R-4, IAEA, Vienna, Austria, 2008.
[10]  IAEA, Deterministic Safety Analysis for NPPs, SSG-2, IAEA, Vienna, Austria, 2009.
[11]  IAEA, Development and Application of Level 1 PSA for NPP, SSG-3, IAEA, Vienna, Austria, 2008.
[12]  IAEA, Development and Application of Level 2 PSA for NPPs, SSG-4, IAEA, Vienna, Austria, 2009.
[13]  IAEA, Severe Accident Management Programs for Nuclear Power Plants, NS-G-2.15, IAEA, Vienna, Austria, 2009.
[14]  L. Morhbach, “Tohoku-Kanto Earthquake and Tsunami on March 11, 2011 and consequences for Northeast Honshu nuclear power plants,” VGB PowerTech, 2011.
[15]  J.-Y. Kim and K.-S. Kang, “Assessment of the safety of ulchin nuclear power plant in the event of tsunami using parametric study,” Nuclear Engineering and Technology, vol. 43, no. 2, pp. 175–186, 2011.
[16]  L. Soffer, S. B. Burson, C. M. Ferrell, R. Y. Lee, and J. N. Ridgely, “Accident source terms for light-water nuclear power plants,” Tech. Rep. NUREG-1465, US NRC, Washington, DC, USA, 1995.
[17]  T. Haste, J. Birchley, E. Cazzoli, and J. Vitazkova, “MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences,” Nuclear Engineering and Design, vol. 236, no. 10, pp. 1099–1112, 2006.
[18]  UNSCEAR, Report of United Nations Scientific Committee on the Effects of Atomic Radiation to the General Assembly, UN, New York, NY, USA, 2000.
[19]  TEPCO, The Great East Japan Earthquake and Current Status of Nuclear Power Stations, Tepco Power-Point, The Tokyo Electric Power Company, 2011.
[20]  USNRC, “Report on the accident at the chernobyl nuclear power station,” Tech. Rep. NUREG-1250, USNRC, Washington, DC, USA, 1987.
[21]  H. Specter and P. Bieniarz, “Is Mark I shell failure really important?—Part one,” Nuclear Engineering and Design, vol. 121, no. 3, pp. 441–446, 1990.
[22]  C. R. Hyman, “Contain calculations of debris conditions adjacent to the BWR Mark I drywell shell during the later phases of a severe accident,” Nuclear Engineering and Design, vol. 121, no. 3, pp. 379–393, 1990.
[23]  IAEA, Integral Design Concepts of Advanced Water Cooled Reactors, Tecdoc-977, IAEA, Vienna, Austria, 1995.
[24]  Z. Hózer, A. Aszódi, M. Barnak et al., “Numerical analyses of an ex-core fuel incident: results of the OECD-IAEA Paks Fuel Project,” Nuclear Engineering and Design, vol. 240, no. 3, pp. 538–549, 2010.
[25]  Z. Hózer, E. Szabó, T. Pintér et al., “Activity release from damaged fuel during the Paks-2 cleaning tank incident in the spent fuel storage pool,” Journal of Nuclear Materials, vol. 392, no. 1, pp. 90–94, 2009.
[26]  Z. Hózer, M. Horváth, M. Kunstár, et al., “Experimental simulation of the Paks-2 cleaning tank incident through separate effect and integral tests,” Nuclear Engineering and Design, vol. 241, pp. 573–581, 2011.
[27]  M. Ramakrishnan, A. John Arul, S. Usha, and C. Senthil Kumar, “Estimation of station blackout frequency for Indian fast breeder test reactor,” Annals of Nuclear Energy, vol. 35, no. 12, pp. 2332–2337, 2008.
[28]  USNRC, “Severe accident risk: an assessment for five US nuclear power plants,” Tech. Rep. NUREG-1150, USNRC, Washington, DC, USA, 1990.
[29]  USNRC, “Initiation of the individual plant examination for severe accident vulnerabilities 10 CFR 50.54(f),” Generic Letter no 88-20, USNRC, Washington, DC, USA, 1989.
[30]  USNRC, “Stress tests specifications,” Tech. Rep., Wenra Task Force, Bruxelles, Belgium, 2011.

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