Share This Article:

Review of safety improvement on sodium-cooled fast reactors after Fukushima accident

Abstract Full-Text HTML Download Download as PDF (Size:825KB) PP. 929-935
DOI: 10.4236/ns.2012.431121    4,524 Downloads   7,938 Views   Citations

ABSTRACT

Several countries are developing and deploying SFRs even after the accident at Tokyo Electric Power Company’s Fukushima Dai-Ichi Nuclear Power Station. However, the Fukushima accident prompted all countries to redefine the fast reactor programs. The drastic safety enhancement is the most important issue to be established. In light of this situation, key essence of the safety improvement is reviewed in this paper by referring the achievements of the recent International Workshop on Prevention and Mitigation of Severe Accidents in SFRs which was held by Japan Atomic Energy Agency (JAEA) in cooperation with the International Atomic Energy Agency (IAEA) in June, 2012 and the findings published in the past journals including those of the International Conference on Fast Reactor and Related Fuel Cycles (FR09) held by IAEA in December, 2009.

Conflicts of Interest

The authors declare no conflicts of interest.

Cite this paper

Takeda, T. , Shimazu, Y. , Foad, B. and Yamaguchi, K. (2012) Review of safety improvement on sodium-cooled fast reactors after Fukushima accident. Natural Science, 4, 929-935. doi: 10.4236/ns.2012.431121.

References

[1] Nakai, R. (2009) Design and assessment approach on advanced SFR safety with emphasis on the core disruptive accident issue. Proceedings of International Conference on Fast Reactor and Related Fuel Cycles (FR09), Kyoto 7-11 December 2009.
[2] Konomura, M. (2012) Severe accident countermeasures of SFR (on Monju). Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga 11-13 June 2012.
[3] Sofu, T. (2012) Importance of Passive safety and role of Monju for the future SFRs. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[4] Nakai, R. (2012) Safety approach based on basic safety characteristics of SFR; harmonization of safety design criteria. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[5] Kubo, S., Shimakawa, Y., Yamano, H. and Kotake, S. (2011) Safety design requirements for safety systems and components of JSFR. Journal of Nuclear Science and Technology, 48, 547-555. doi:10.1080/18811248.2011.9711732
[6] Aoto, K., Uto, N., Sakamoto, Y., Ito, T., Toda, M. and Kotake, S. (2011) Design study and R & D progress on Japan sodium-cooled fast reactor. Journal of Nuclear Science and Technology, 48, 463-471. doi:10.1080/18811248.2011.9711720
[7] Sato, I., Tobita, Y., Konishi, K., Kamiyama, K., Toyooka, J., Nakai, R., Kubo, S., Kotake, S., Koyama, K., Vassiliev, Y., Vurim, A., Zuev, V. and Kolodeshnikov, A. (2011) Safety strategy of JSFR eliminating severe recriticality events and establishing in-vessel retention in the core disruptive accident. Journal of Nuclear Science and Technology, 48, 556-566. doi:10.1080/18811248.2011.9711733
[8] IAEA (2005) Status of innovative small and medium sized reactor designs. IAEA TECDOC-1485.
[9] IAEA (2007) Status of small reactor designs without onsite refueling. IAEA TECDOC-1536, 2, 395-444.
[10] Beils, S., Carluec, B., Devictor, N., Fiorini, G. L. and Sauvage, J. F. (2011) Safety approach and R & D program for future French sodium-cooled fast reactors. Journal of Nuclear Science and Technology, 48, 510-515. doi:10.1080/18811248.2011.9711727
[11] Palmiotti, G., Salvatores, M. and Assawaroongruengchot, M. (2011) Impact of the core minor actinide content on fast reactor reactivity coefficients. Journal of Nuclear Science and Technology, 48, 628-634. doi:10.1080/18811248.2011.9711743
[12] Carluec, B., Lo Point, P., Mariteau, P. and Capelle, S. (2012) Severe accident countermeasure of SFR. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[13] International Nuclear Safety Advisory Group (1996) Defense-in-depth in nuclear safety. INSAG Series 10, IAEA, Vienna.
[14] Shvetsov, I. (2012) Russian safety approach for NPPs with SFR. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[15] Poplavsky, V.M., Matveev, V.I., Eliseev, V.A., Kuznetsov, I.A., Volkov, A.V., Shvetsov, Y.E., Khomyakov, Y.S. and Tsiboulia, A.M. (2011) Studies on influence of sodium void reactivity effect on the concept of the core and safety of advanced fast reactor. Journal of Nuclear Science and Technology, 48, 538-546. doi:10.1080/18811248.2011.9711731
[16] Chellapandi, P. (2012) Overview of Indian FBR programme. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[17] Kumar, P. (2012) Proposed activities at PFBR in the wake of Fukushima accident. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[18] Ren, L. (2012) Status of China National SFR Program. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[19] Ren, L. (2012) Severe accidents analysis in CEFR and technology gaps. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[20] Sofu, T. (2012) US approach for inherent prevention and mitigation of SFR severe accidents. Proceedings of JAEA-IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[21] Wigeland, R.A. and Cahalan, J.E. (2011) Inherent prevention and mitigation of severe accident consequences in sodium-cooled fast reactors. Journal of Nuclear Science and Technology, 48, 516-523. doi:10.1080/18811248.2011.9711728
[22] Bychkov, A. (2012) Fast reactors and closed fuel cycle: safety technologies and sustainability. Proceedings of JAEA- IAEA International Workshop on Prevention and Mitigation of Severe Accidents in Sodium-Cooled Fast Reactors, Tsuruga, 11-13 June 2012.
[23] IAEA (2011) GIF-IAEA/INPRO Workshop on Safety Aspects of Sodium-Cooled Fast Reactors, IAEA, Vienna.
[24] IAEA/INPRO (2012) Technical meeting on impact of Fukushima event on current and future fast reactor designs: The INPRO methodology and collaborative projects related to fast reactor cooling. Hermholtz Zentrum Dresden Rossendorf (HZDR), IAEA, Vienna.

  
comments powered by Disqus

Copyright © 2019 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.