Nuclear Engineering and Technology

  • 제52권11호
  • /
  • Pages.2511-2521
  • /
  • 2020
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Post-Fukushima challenges for the mitigation of severe accident consequences

  • 투고 : 2019.08.16
  • 심사 : 2020.04.28
  • 발행 : 2020.11.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

The Fukushima accident is characterized by the fact that three reactors at the same site experienced reactor vessel failure and the accident resulted in significant radiological release to the environment, which was about 1/10 of the Chernobyl releases. The safe removal of fuel debris in the reactor vessel and Primary Containment Vessel (PCV) and treatment of huge amount of contaminated water are the major issues for the decommissioning in coming decades. Discussions on the new researches efforts being carried out in the area of investigation of the end state of fuel debris and Boling Water reactor (BWR) specific core melt progression, development of technologies for the mitigation of radiological releases to comply with the strengthened safety requirement set after the Fukushima accident are discussed.

키워드

참고문헌

  1. IAEA, The Fukushima Daiichi Accident, vols. 1 - 4, 2015.
  2. J. Rempe, et al., Safety insights from forensics evaluations at Daiichi, Nuclear Materials and Energy 10 (2017) 18-34. https://doi.org/10.1016/j.nme.2016.08.010
  3. D. Peko, et al., Working together to enhance nuclear reactor safety, Nucl. News 36-42 (April 2018).
  4. M. Pellegrini, et al., Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project, in: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, 2019. August 18-22.
  5. NEA/CSNI/R, Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project), Phase I Summary Report, vol. 18, 2015. February 2016.
  6. Sandia National Laboratories, R. Gauntt, et al., MELCOR Computer Code Manuals Vol. 1: Primer and Users' Guide. Version 1.8.6. NUREG/CR-6119. Rev 3. SAND2005-5713, September 2005.
  7. Tae-Woon Kim, et al., Estimation of in-plant source term release behaviors from Fukushima Daiichi reactor cores by forward method and comparison with reverse method, J. Radiat. Protect. Res. 42 (2) (2017) 114-129. https://doi.org/10.14407/jrpr.2017.42.2.114
  8. Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company, July 23, 2012. http://www.cas.go.jp/jp/seisaku/icanps/eng/.
  9. https://www7.tepco.co.jp/wp-content/uploads/hd03-02-04-001-001-05-handouts_150319_01-e.pdf.
  10. https://www7.tepco.co.jp/wp-content/uploads/hd03-02-03-001-d190228_01-e.pdf.
  11. https://fdada.info/en/home2/accident2/measured2/ag_other-en/#p2.
  12. JinHo Song, An assessment on the environmental contamination caused by the Fukushima accident, J. Environ. Manag. 206 (2018) 846-852. https://doi.org/10.1016/j.jenvman.2017.11.068
  13. http://www.tepco.co.jp/en/decommission/progress/watertreatment/index-e.html.
  14. http://www.tepco.co.jp/en/decommission/progress/watertreatment/images/tankarea_en.pdf.
  15. https://www.meti.go.jp/english/earthquake/nuclear/decommissioning/pdf/20200203_current_status.pdf.
  16. https://www7.tepco.co.jp/wp-content/uploads/handouts_180726_03-e.pdf.
  17. Electric Power Research Institute, Analysis of Three Mile Island - Unit 2 Accident, Nuclear Safety Analysis Center, 1980. NSAC-80-1.
  18. D.W. Akers, et al., TMI-2 core materials and fission product inventory, Nucl. Eng. Des. 118 (1990) 451-461. https://doi.org/10.1016/0029-5493(90)90046-Z
  19. D.L. Luxat, et al., MAAP-MELCOR crosswalk phase 1 study, Nucl. Technol. 196 (3) (2016) 684-697. https://doi.org/10.13182/NT16-57
  20. A. Quaini, et al., Contribution to the thermodynamic description of the coriume the U-Zr-O system, J. Nucl. Mater. 501 (2018) 104-131. https://doi.org/10.1016/j.jnucmat.2018.01.023
  21. S.V. Bechta, et al., Corium phase equilibria based on MASCA, METCOR and CORPHAD results, Nucl. Eng. Des. 238 (2008) 2761-2771. https://doi.org/10.1016/j.nucengdes.2008.04.018
  22. IRSN, NucleaToolbox 1, 3 User's Manual, 2016.
  23. J.M. Seiler, B. Tourniaire, F. Defoort, K. Froment, Consequences of material effects on in-vessel retention, Nucl. Eng. Des. 237 (2007) 1752-1758. https://doi.org/10.1016/j.nucengdes.2007.03.007
  24. Mo An Sang, et al., Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant, J. Nucl. Mater. 478 (2016) 164-171. https://doi.org/10.1016/j.jnucmat.2016.06.011
  25. S.W. Hong, et al., Application of cold crucible for melting of UO2/ZrO2 mixture, Mater. Sci. Eng. A357 (2003) 297-303.
  26. K. Fukuda, et al., Dose analysis in criticality accident of fuel debris in water, Nucl. Sci. Eng. 194 (3) (2020) 181-189. https://doi.org/10.1080/00295639.2019.1665459
  27. NEA/CSNI/R, Status Report on Filtered Containment Venting, Committee on the Safety of Nuclear Installations, vol. 7, Organisation for Economic Co-operation and Development/Nuclear Energy Agency, 2014, 2014.
  28. I. Sung, Kim, et al., Introduction of filtered containment venting system experimental facility in KAERI and results of aerosol test, Nucl. Eng. Des. 326 (2018) 344-353. https://doi.org/10.1016/j.nucengdes.2017.11.036
  29. T. Lind, et al., A summary of fission- product- transport phenomena during SGTR severe accidents, paper 27826, in: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2019. Portland, OR, August 18-22.

피인용 문헌

  1. Current State of Research in the Field of Detritiation of Technological Water Flows: A Review vol.55, pp.6, 2021, https://doi.org/10.1134/s0040579521060051