Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type
International Journal of Energy and Power Engineering
Volume 2, Issue 3, June 2013, Pages: 113-120
Received: May 17, 2013;
Published: Jul. 10, 2013
Views 3274 Downloads 138
Yu. M. Golovchenko, Joint Stock Company “State Scientific Centre Research Institute of Atomic Reactors”, JSC “SSC RIAR”, Dimitrovgrad, 433510, Russia
The article deals with the initial requirements for metal fuel elements and commercial reactors using this type of elements: high smear density of fuel, high technological effectiveness of fuel, fuel column and fuel elements; interchangeability of metal fuel elements and oxide fuel elements; achievement of fuel breeding ratio of the core BRC ~1.0; prolongation of refuelling cycle up to Tc~11 months. The article presents content and results of examinations of radiation-thermal effects in U fuel column elements and UPu fuel column elements: irradiation of breeding and fuel elements in the BOR-60 and BN-350 reactors; research of macroeffects of radiation growth, radiation swelling, fuel-cladding chemical interaction. Applicability of the obtained results for developing advanced BN-reactors with heterogeneous cores of various types was discussed: with by FA heterogenization of the core (BFAH); intra FA heterogenization of the core (IFAH); intra fuel element heterogenization (IFEH).
Yu. M. Golovchenko,
Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type, International Journal of Energy and Power Engineering.
Vol. 2, No. 3,
2013, pp. 113-120.
Status and Trends of Nuclear Fuels Technology for Sodium Cooled Fast Reactors. IAEA Nuclear Energy Series № NF-T-4.1, Vienna.2011
K. Devan, Debanwita Paul, Abhitab Bachchan et al. Physics Design and Safety Studies of a 320 MWt Experimental Metal FBR// International Conference FR 13, Paris, 4-7 March 2013, T 01 Paper 299.
E.R. Cramer, A.L. Pitner. In situ observation of axial irradiation growth in liquid-metal reactor metal fuel//Trans. Amer. Nucl. Soc. 1989, 60, 306-307.
S.V. Pavlov, A.V. Sukhikh, S.S.Sagalov. Gamma-spectrometry in reactor material-science. Dimitrovgrad: JSC "SSC RIAR", 2012, 314p.
Arun Kumar. Development , fabrication and characterization of fuels for Indian fast reactor programme //International Conference FR 13, Paris, 4-7 March 2013,T 05, Paper № 025.
G. Ravisankar. Metal alloy and Sphere-Pac MOX test fuel fabrication for irradiation in FBTR.// International Conference FR 13, Paris, 4-7 March 2013, T 05 Paper 213.
Y.M. Golovchenko. Scientific validation of absorbing, breeding and fuel elements with metal uranium columns for fast reactors of the BN type. Dissertation, M., 2002.
Su S.F., Orechwa Y., Barthold W.P. Configuration optimization of high-performance 1000-MWe oxide heterogeneous cores. – Annual Meeting of American Nuclear Society, Las Vegas. Nev., 1980. Summaries. – «Trans. Amer. Nucl. Soc.», 1980, 34, 780-781.
O.D. Kazachkovsky, V.A. Tsykanov, V.B. Lyitkin, I.S. Slesarev. Fast breeder reactors in nuclear power development. – «ENS – 3 Proc.: Int. Conf. New. Dir. Nucl. Energy Emphasis Fuel Cycles, Brussels, 26-30 Apr., 1982. Proc. Plenary Sess.» Brussels, 1982, 495-502.
M.F.Troyanov, A.A.Rineisky, A.A.Kamaev. Possible ways of achieving limit characteristics of fast reactors safety. Atomnaya energiya,V.66, No.4, April 1986, 235-238.
P.N.Alexeev, Yu.A.Zverev, A.G.Morozov, V.V.Orlov et al. Concept of new generation reactor of high-level safety with liquid-metal coolant LMFR. Atomnaya energiya, V.66, No.3, March 1989, 155-158
Y.M. Golovchenko. Experience of Developments and Tests, Application of High-Dence Metallic Fuel in Fast Reactors // Proceedings of GLOBAL 2011, Makuhan,Japan, Dec. 11-16, 2011. Paper № 392457.
A.A.Mayorshin. Vibropac oxide fuel pins– Dimitrovgrad: FSUE "SSC RF RIAR" 2007. – 327 p.
American company TerraPower can become a new partner of RIAR.//http://www. atomic-energy.ru/news/2010/09/06/13604.