PROSPECTS OF VVERSKD IN A CLOSED FUEL CYCLE

UDC: 
621.311.25:621.039.51

Issue of journal:

Abstract: 

IAEA supervised a research project (from early in 2005 till late in 2007) on
innovative nuclear reactors and fuel cycles (International Project on Innovative Nuclear
Reactors and Fuel Cycles – INPRO), 8 countries with developed atomic power taking part
in it. The aim of the project was to evaluate a nuclear power system based on a closed
fuel cycle (CFC) with fast reactors in terms of its evolution, specification of
implementation stages and duration, providing a basis and a field for joint R&D work.
The countries agreed to use the commercial system CNFCFR (Commercial Nuclear Fuel
CyclesFast Reactors) as a standard in evaluation. The system is ready for wide
application in the upcoming 23 decades and is based on proven technologies such as
sodium coolant, pelletized mixed oxide (МОХ) fuel and advanced technology for aquatic
processing.
Despite the common fundamentals of the CNFCFR system, there are significant differences between the nuclear power systems existing in the countries participating
in the joint studies and between the strategies for their development, which is the
reason for the differences in the implementation of closed fuel cycle. In some countries
it is proposed that, besides sodium, gas and lead should be used. In addition to МОХ
fuel, consideration is given to a denser nitride and metal fuel, together with different
UPu, UTh fuel cycles.
Since 2000 many countries have been supporting development of G4 supercritical
watercooled thermal and fast neutron reactors (Supercritical WaterCooled Reactors –
SCWR). It is planned to have built demonstration reactors followed by commercial NPPs
by 2025. Development of SCWR reactors will bring about changes in working out AE
strategy as well as CFC process in some countries.
The report examines peculiarities of implementing closed fuel cycle in Russia,
implementation stages and duration, associated problems and possible ways of dealing
with them; it also proposes solutions for optimizing fuel cycle.

References: 
A Technology Roadmap for Generation IV Nuclear Energy Systems. 2002, 91 p. Available at: http://www.gen4org/PDFs/GenIVRoadmap.pdf,
Kirillov P.L., Poro I. Generation IV nuclear reactors as the basis for the global electricity production in the future. Nuclear energy technology abroad. 2014, no.2, pp. 312 (in Russian).
Assessment of nuclear energy systems based of a closed nuclear fuel cycle with fast reactors. Report IAEA. January 2010, Wienna – TECDOC1639.
The new program Rosatom. Periodical Strana «Rosatom» 19.03.2012 (in Russian).
«Rosatom» creates reactors running on spent fuel. Periodical Nuclear strategy 06.08.2012 (in Russian).
Gonchar N.I., Pankratov D.V. Characterization of LMC output polonium into the gas phase from the experimental data SSC RFIPPE/Report on the conference: «Thermophysics2013». – Obninsk, 2013 (in Russian).
Krjukov F.N., Nikitin O.N., Kuzmin S.V., Belyaeva A.V., Malceva E.B., Gilshutdinov I.F., Grin P.I. Condition nitride fuel after irradiation in fast reactors. Atomnaja Energija. 2012, v. 112, iss. 6, pp. 336341.
Lopatkin A.V., Orlov V.V., SiliNovitskii A.G., Filin A.M., Bibilishvili Yu.K., Rogozin B.D., Leontev B.F. Fuel cycles reactors BREST. Atomnaja Energija. 2000, v. 89, iss. 4, pp. 308–314.
Designing fast leadcooled reactor (LFR): safety, neutron physics, thermal hydraulics, mechanical designs, fuel, reactor core design and installation. Novosti atomnoj nauki i tehniki. 08.10.2011, no. 225228. Obninsk, IPPE Publ. (in Russian).
Safutin V., Zavidskii M., Kirsanov A. National service industry SNF. Jadernoe obshhestvo. 2000, no. 56, pp. 5762 (in Russian).
Oka Y., Koshizuka S. Design Concept of OnceThrough Cycle SupercriticalPressure Light Water Cooled Reactors/Proceedinge of the First International Symposium on Supercritical WaterCooled Reactors. – 69 Nov. 2000. – Tokyo, Japan.
Yetisir M., Gaudet M., Rhodes D. Development and Integration of Canadian SCWR Concept with CounterFlow Fuel Assembly/ISSWCR6. – 0307 March 2013 – Shenzhen, China – Paper 13059.
Tian X., Tian W., Zhu D., Qiu S., Su G. A stability analysis of supercritical watercooled reactor CSR1000/ISSCWR6. – 0307 March 2013. – Shenzhen, China. – Paper 13044.
Zhang Peng, Wang Kan, Yu Ganglin Utilization of Different Fuel in Supercritical Fast Reactor/ISSCWR6. – 0307 March 2013. – Shenzhen, China. – Paper 13083.
Glebov A.P., Klushin A.V. Reactor with fast resonance spectrum cooled by water at supercritical pressure and twopass coolant flow scheme. Atomnaja Energija. 2006, v. 100, iss. 5, pp. 349–355.
Ryjov S.B., Mokhov V.A., Nikitenko M.P. The concept of singleVVERSKD with body reactor cooled by supercritical water/Report on the 5th International Symposium: ISSCWR5. – 1316 march 2011. – Vancouver, Canada.
Alexander P. Glebov, Alexey V. Klushin, Yuriy D. Baranaev, Pavel L. Kirillov Presearch of Features of UPuTh Fuel Cycle and its use for Burning up of Minor Actinides in Supercritical WaterCooled Reactor with Fast Neutron Spectrum/ICONE21. – 29 July2 August 2013. – Chengdu, China. – Paper 16888.
Baranaev Yu.D., Glebov A.P., Klushin A.V. Reactor core with fastresonance neutron spectrum with supercritical water pressure. Patent for an invention № 2485612, 2013, RU 2 485 612 С1 (in Russian).

For full access to information log in or register here.