Deployment of SMRs in Japan

Except for the small nuclear power stations constructed around 1970, there has been no deployment of SMRs in Japan. After the severe earthquake on March 11, 2011, followed by the severe accident at the Fukushima Dai-ichi nuclear power station, deployment of nuclear power plants has basically been frozen in Japan, including deployment of SMRs in Japan. Since the policy for nuclear energy utilization has been under discussion in Japan after the Fukushima Dai-ichi accident and has not yet been determined, it is difficult to present a perspective for the SMR deployment in Japan at this time (February 2014).

However, the activities for deployment of some Japanese SMR concepts in other countries are continuing. One of them is the 4S (described in Section 19.3.5) deployment activity in Alaska, USA, which is under preliminary review by the US Nuclear Regulatory Commission. The other is the HTR50S (mentioned in Section 19.3.4) deployment activity in Kazakhstan, to be realized in the 2020s.

19.2 Future trends

As mention in the previous section, the Japanese policy for the nuclear energy utilization has been under discussion since the Fukushima Dai-ichi accident. It is difficult to present the likely future trend in Japan. After the Fukushima Dai-ichi accident, safety requirements have become more severe. Some SMR design concepts may need to be changed or checked against the new requirements.

Since the deployment of nuclear power plants is not expected to be easy in Japan, the SMR deployment abroad would be one likely future trend in Japan. In such a situation, there are two possibilities for the SMR deployment. One is the use based on the experienced LWR-based reactor. The other would be the use of new and non-LWR-based reactor. It can be said that the Japanese SMR have the potential to answer both possibilities.

19.3 Sources of further information and advice

A valuable source of further information is the new revision of the IAEA-TECDOC on the SMR status in the world. The revision of the TECDOC has been issued around every five years. The websites of the Japanese vendors of Mitsubishi, Toshiba and Hitachi would be other information sources, using keywords of the SMR and each reactor, such as IMR, CCR, DMS and 4S. The JAEA website is also valuable for the gas-cooled concepts of GTHTR300 and HTR50S. Also, the papers submitted to the international conferences, such as ICONE, ICAPP and ANS topical meeting on the SMR, would be valuable.

References

Hannerz, K., et al. (1986): PIUS LWR design progress: IAEA Technical Committee Meeting on Advances in Light Water Reactor Technology, Washington, DC, Nov. 17-19, 1986. Heki, H., et al. (2005): Development status of compact containment BWR plant, Proceedings of ICAPP’05, Seoul, Korea, May 15-19, 2005, Paper 5174.

Hibi, K., etal. (2005): Improvement of reactor design on integrated modular water reactor (IMR) development, Proceedings of ICAPP’05, Seoul, Korea, May 15-19, 2005, Paper 5215.

IAEA (2006): Status of innovative small and medium sized reactor designs 2005, IAEA — TECDOC-1485.

Katanishi S., et al. (2003): Safety design philosophy of gas turbine high temperature reactor (GTHTR300), Transactions of Atomic Energy Society of Japan, 2(1), 55-67 (in Japanese).

Kataoka, Y., et al. (1988): Conceptual design and thermal-hydraulics of natural circulation boiling water reactors, Nuclear Technology, 82(2), 147-156.

Kawabata, Y., et al. (2008): The plant feature and performance of DMS (double MS: modular simplified & medium small reactor), Proceedings of ICONE16, Orlando, USA, May 11-14, 2008, ICONE16-48949.

Kudo, F., et al. (1987): Preliminary study of inherently safe integrated small PWR, Abstracts of 1987 Annual Meeting of Atomic Energy Society of Japan, E48 (in Japanese).

Kunitomi, K., et al. (2002): Design study on gas turbine high temperature reactor (GTHTR300), Transactions of Atomic Energy Society of Japan, 1(4), 352-360 (in Japanese).

Kunitomi, K., et al. (2004): Japan’s future HTR — the GTHTR300, Nuclear Engineering and Design, 233, 309-327.

Kusunoki, T., et al. (2000): Design of advanced integral-type marine reactor MRX, Nuclear Engineering and Design, 201, 155-175.

Makihara, Y., et al. (1991): On Mitsubishi small and medium sized reactor MS-600, Abstracts of 1991 Annual Meeting of Atomic Energy Society of Japan, SO3 (in Japanese).

Nagasaka, H., et al. (1990): Study of a natural-circulation boiling water reactor with passive safety, Nuclear Technology, 92(2), 260-268.

Nakagawa, S., et al. (2004): Safety demonstration tests using high temperature engineering test reactor,’ Nuclear Engineering and Design, 233, 301-308.

Oda, J., et al. (1986): A conceptual design of intrinsically safe and economical reactor, IAEA Technical Committee Meeting on Advances in Light Water Reactor Technology, Washington, DC, Nov. 17-19, 1986.

Ohashi, H., et al. (2011): Conceptual design of small-sized HTGR system for steam supply and electricity generation (HTR50S), Proceedings of ASME 2011 Small Modular Reactor Symposium, Washington, DC, Sept. 28-30, 2011, SMR2011-6558.

Okazaki, T., et al. (2011): A study for small — medium LWR Development of JAPC, Proceedings of ICONE19, Osaka, Japan, October 24-25, 2011, ICONE19-43646.

Okubo, T. (2011): Status of SMR Development in Japan, 1st ANS SMR 2011 Conference, Washington, DC, November 1-4, 2011.

Saito, S., et al. (1994): Design of High Temperature Engineering Test Reactor (HTTR), JAERI-Report 1332.

Sako, K. (1988): Conceptual design of SPWR, Proceedings on ANS International Topical. Meeting on Safety of Next Generation Power Reactors, Seattle, USA, May 1-5, 1988.

Shimizu, K., et al. (2011): Small-sized high temperature reactor (MHR-50) for electricity generation: Plant concept and characteristics, Progress in Nuclear Energy, 53, 846­854.

Tsuboi, Y., et al. (2009): Development of the 4S and related technologies (1) — Plant system overview and current status, Proceedings of ICAPP’09, Tokyo, Japan, May 10-14, 2009, Paper 9214.

Tsuboi, Y., et al. (2012): Design of the 4S reactor, Nuclear Technology, 178, 201-217.