SVBR-100 Nuclear Technology as a Possible Option for Developing Countries

Vladimir Petrochenko¹, Georgy Toshinsky^1,2*, Oleg Komlev¹

¹JSC “AKME-Engineering”, Moscow, Russia.
²FSUE SSC RF-IPPE, Obninsk, Russia.

DOI: 10.4236/wjnst.2015.53022                

Abstract

Many developing countries need ecologically clean power sources (PS). The nuclear power plants are such sources. However, a great number of the developing countries do not possess developed large capacity power systems. Moreover, currently in the developing countries, there are no highly skilled personnel to provide construction and reliable and safe operation of the nuclear plants, which are complex and potentially hazardous systems. In some countries, the level of terroristic threat is extremely high. For that reason, there are specific requirements to the nuclear PSs intended for use in the developing countries. In the presented report, the specific requirements which must be met by the NPT proposed for use in developing countries are formulated, basic statements of the SVBR-100 concept are presented, design and principal scheme of the reactor fa-ility are described, major characteristics of SVBR-100 are summarized.

Keywords

SVBR-100, Reactor, Nuclear Power Technology, Nuclear Power Plant, Inherent Self-Protection, Passive Safety

Conflicts of Interest

The authors declare no conflicts of interest.

References

[1]	Spievak, I. and Weinberg, A.M. (1985) Inherently Safe Reactors. Annual Review of Energy, 10, 431-462. http://dx.doi.org/10.1146/annurev.eg.10.110185.002243
[2]	Forsberg, C.W. and Weinberg, A.M. (1990) Advanced Reactors, Passive Safety, and Acceptance of Nuclear Energy. Annual Review of Energy, 15, 133-152. http://dx.doi.org/10.1146/annurev.eg.15.110190.001025
[3]	Arutyunyan, R.V. (2013) Have We Got Safety Culture? Atomnaya Strategiya, 83, 9-11. http://www.proatom.ru/
[4]	Nuclear Terrorism. http://www.gochs.info/p669.htm
[5]	IAEA (2006) Advanced Nuclear Plant Design Options to Cope with External Events. IAEA-TECDOC-1487. http://www-pub.iaea.org/MTCD/publications/PDF/te_1487_web.pdf
[6]	Ammirabile, L. European Project SARGEN_IV: Safety Approach and Assessment of GEN IV Reactors. http://www.iaea.org/NuclearPower/Downloadable/Meetings/2013/2013-02-26-02-27-TM-SFR/day-1/4-L.Ammirabile-EC.pdf
[7]	Toshinsky, G.I., Komlev, O.G., Tormyshev, I.V. and Petrochenko, V.V. (2013) Effect of Potential Energy Stored in Reactor Facility Coolant on NPP Safety and Economic Parameters. World Journal of Nuclear Science and Technology, 3, 59-64. http://www.scirp.org/journal/wjnst
[8]	Toshinsky, G.I., Komlev, O.G., Stepanov, V.S., et al. (2007) Principles of Providing Inherent Self-Protection and Passive Safety Characteristics of the SVBR-75/100 Type Modular Reactor Installation for Nuclear Power Plants of Different Capacity and Purpose. Paper No. 175598. International Conference Advanced Nuclear Fuel Cycles and Systems (GLOBAL’07), Boise, 9-13 September 2007.
[9]	Bolhovitinov, V.D., Pankratov, D.V., Toshinsky, G.I., et al. (2003) Assessment of Radiation Consequences Caused by Large Tightness Failure in the Primary Circuit Gas System of RF SVBR-75/100 with Simultaneous Coolant Heating up to 600°C. Paper No. 2203 (CD-ROM), 3rd Conference Heavy-Liquid Metal Coolants in Nuclear Technologies (HLMC-2003) within the Frameworks of Russian Scientific and Technical Forum Nuclear Fast Neutron Reactors, Obninsk, 4-12 December 2003.
[10]	IAEA (2012) Safety of Nuclar Power Plants: Design, Specific Safety Requirements. IAEA Safety Standards Series No. SSR-2/1.
[11]	Zrodnikov, A.V., Toshinsky, G.I., Stepanov, V.S., et al. (2008) Innovative Nuclear Technology Based on Modular Multi-Purpose Lead-Bismuth Cooled Fast Reactors. Progress in Nuclear Energy, 50, 170-178. http://dx.doi.org/10.1016/j.pnucene.2007.10.025
[12]	Zrodnikov, A.V., Toshinsky, G.I., Stepanov, V.S., et al. (2004) Lead-Bismuth Reactor Technology Conversion: From Nuclear Submarine Reactors to Power Reactors and Ways to Increase the Investment Attractiveness of Nuclear Power Based on Fast-Neutron Reactors. Proceedings of IAEA International Conference “Fifty Years of Nuclear Power—The Next Fifty Years”, Report IAEA-CN-A3, Obninsk.
[13]	Novikova, N.N., Komlev, O.G. and Toshinsky, G.I. (2006) Neutronic and Physical Characteristics of Reactor SVBR-75/100 with Different Types of Fuel. Proceedings of International Congress on Advances in Nuclear Power Plants, CD-ROM, Paper No. 6355, Reno, 4-8 June 2006.
[14]	Gromov, B.F., Toshinsky, G.I., Zrodnikov, A.V., Dragunov, Yu.G., Stepanov, V.S., et al. (2001) Nuclear Power Complex Based on SVBR-75/100 Small Reactors Cooled by Lead-Bismuth Liquid Metal Coolant. Competitiveness, Simplified Life Cycle, Safety, Non-Proliferation. Proceedings of IAEA International Seminar on Status and Prospects for Small and Medium Sized Reactors, Cairo, 27-31 May 2001.
[15]	Zrodnikov, A.V., Toshinsky, G.I., Komlev, O.G., et al. (2006) Nuclear Power Development in Market Conditions with Use of Multi-Purpose Modular Fast Reactors SVBR-75/100. Nuclear Engineering and Design, 236, 1490-1502. http://dx.doi.org/10.1016/j.nucengdes.2006.04.005