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Accident Analysis and Issues

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The Fukushima Daiichi Nuclear Accident

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Abstract

Chapters 2–5 presented an outline of Nuclear Power Station, an overview of the accident at the Fukushima Daiichi NPS, an overview of the events that took place at nuclear power stations other than the Fukushima Daiichi, and responses to the accident outside the power station based on fact. In keeping with these facts, Chap. 6 analyzes and evaluates the accident from various perspectives. First, the items of the analysis in Chap. 6 are explained, the accident progression behavior is simulated, and the findings from the evaluation of the releases of radioactive materials during the accident are presented in Sect. 6.1. Second, each item is analyzed and evaluated and the relevant issues are addressed in Sect. 6.2 and subsequent sections.

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Notes

  1. 1.

    Interim Report of the Special Committee on Safety Goals for Nuclear Safety Installations in Japan, Commission,” Special Committee on Safety Goals, Nuclear Safety Commission, December 2003.

  2. 2.

    “Scientific and reasonable rules” is a typical representation, but “reasonable” often elicits misunderstanding. “logical” is therefore used in this paragraph as rules that are logically structured based on certain concept and principle.

  3. 3.

    NUREG-1560, Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance, December (1997).

  4. 4.

    NUREG-1742, Perspectives Gained from the Individual Plant Examination of External Events (IPEEE) Program, April 2002.

  5. 5.

    IAEA, Severe Accident Management.

  6. 6.

    Review Guide for Safety Design of Nuclear Power Reactors, Nuclear Safety Commission.

  7. 7.

    Accident Management, Nuclear Safety Commission, 1992 (revised in 1997, abolished in 2010)

  8. 8.

    “Multiple defence” is the term used in the original text, but “defence in depth” is used in this document to avoid misunderstanding that defence is achieved by redundant installation of engineering facilities.

  9. 9.

    http://www.nsr.go.jp/committee/kisei/h24fy/data/0032_10.pdf.

  10. 10.

    For example, classification by significance of risk and a relevant response is selected to achieve goals.

  11. 11.

    Resilience: Methods and capacity of restoring the required function to safety assurance level as a system to respond to an incident or accident.

  12. 12.

    Flexibility of responses.

  13. 13.

    According to the classification of importance, the IC as the “safety equipment” is “classified as (1) the building, system or equipment used to shut down the reactor in an emergency, remove residual heat, prevent overpressure at the reactor coolant boundary, and mitigate significant impact of radiation on local residents,” and one of residual heat removal systems in BWR, specifically as “(4) the building, system or equipment to remove residual heat after reactor shutdown.”

  14. 14.

    AESJ standard “Development, maintaining and improvement of severe accident management in nuclear power plants:2014” (Note: The accident management and severe accident management are used as the same term here.)

  15. 15.

    Protective actions which can be implemented within days to weeks and still be effective.

  16. 16.

    Radiation source accident in Brazil, 1987.

  17. 17.

    Criticality accident in Japan, 1999 at the JCO uranium-conversion plant in Tokaimura.

  18. 18.

    Protective actions which must be taken promptly (normally within hours) in order to be effective, and the effectiveness of which will be markedly reduced if they are delayed.

  19. 19.

    Predetermined conditions and instrument readings in the nuclear power plant, if exceeded the staff will immediately notify off-site officials to issue a coordinated response order.

  20. 20.

    Government Accident Investigation Committee Report Chapter V.

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      Appendix: Items Related to Accident Progression That Require Further Investigation and Consideration

      Appendix: Items Related to Accident Progression That Require Further Investigation and Consideration

      Events progressed concerning several rector cores and spent fuel pools in the accident at the Fukushima Daiichi Nuclear Power Station, while various accident responses were conducted. Consequently, the development of the accident was very complicated.

      In addition, due to high level of radiation particularly in the reactor building, detailed investigations including human access remain limited in some areas. Details of the status of the inside of the containment vessels in Units 1, 2, and 3 are unknown. From the above, this section summarizes topics concerning the accident progress which particularly need to be investigated and studied in detail. Such summary seems to be important during further investigation in future.

      Facts related to the accident were checked focusing on 14 reports [96–109] released as reference materials. Perspectives which are important from an R&D perspective are summarized as remarks. Topics to be studied include (1) those that have not been fully investigated yet, those with room for further examination, or those for which reasonable explanations are currently difficult, and (2) those that seem reasonable but evidence is lacking so far.

      Summarized topics are listed in Table 6.A.

      Table 6.A Items requiring more detailed investigation in future in the events of the Fukushima Daiichi nuclear power station accident
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      Atomic Energy Society of Japan. (2015). Accident Analysis and Issues. In: The Fukushima Daiichi Nuclear Accident. Springer, Tokyo. https://doi.org/10.1007/978-4-431-55160-7_6

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