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Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type

Received: 17 May 2013     Published: 10 July 2013
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Abstract

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).

Published in International Journal of Energy and Power Engineering (Volume 2, Issue 3)
DOI 10.11648/j.ijepe.20130203.15
Page(s) 113-120
Creative Commons

This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.

Copyright

Copyright © The Author(s), 2013. Published by Science Publishing Group

Keywords

Fast Reactors,Heterogeneous Oxide-Metal Cores, Metal Fuel;Breeding and Fuel Elements, Irradiation in BOR-60 and BN-350, Postirradiation Examinations

References
[1] Status and Trends of Nuclear Fuels Technology for Sodium Cooled Fast Reactors. IAEA Nuclear Energy Series № NF-T-4.1, Vienna.2011
[2] 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.
[3] 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.
[4] S.V. Pavlov, A.V. Sukhikh, S.S.Sagalov. Gamma-spectrometry in reactor material-science. Dimitrovgrad: JSC "SSC RIAR", 2012, 314p.
[5] 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.
[6] 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.
[7] 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.
[8] 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.
[9] 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.
[10] 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.
[11] 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
[12] 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.
[13] A.A.Mayorshin. Vibropac oxide fuel pins– Dimitrovgrad: FSUE "SSC RF RIAR" 2007. – 327 p.
[14] American company TerraPower can become a new partner of RIAR.//http://www. atomic-energy.ru/news/2010/09/06/13604.
Cite This Article
  • APA Style

    Yu. M. Golovchenko. (2013). 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, 2(3), 113-120. https://doi.org/10.11648/j.ijepe.20130203.15

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    ACS Style

    Yu. M. Golovchenko. Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type. Int. J. Energy Power Eng. 2013, 2(3), 113-120. doi: 10.11648/j.ijepe.20130203.15

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    AMA Style

    Yu. M. Golovchenko. Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type. Int J Energy Power Eng. 2013;2(3):113-120. doi: 10.11648/j.ijepe.20130203.15

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  • @article{10.11648/j.ijepe.20130203.15,
      author = {Yu. M. Golovchenko},
      title = {Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type},
      journal = {International Journal of Energy and Power Engineering},
      volume = {2},
      number = {3},
      pages = {113-120},
      doi = {10.11648/j.ijepe.20130203.15},
      url = {https://doi.org/10.11648/j.ijepe.20130203.15},
      eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20130203.15},
      abstract = {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).},
     year = {2013}
    }
    

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  • TY  - JOUR
    T1  - Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type
    AU  - Yu. M. Golovchenko
    Y1  - 2013/07/10
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    N1  - https://doi.org/10.11648/j.ijepe.20130203.15
    DO  - 10.11648/j.ijepe.20130203.15
    T2  - International Journal of Energy and Power Engineering
    JF  - International Journal of Energy and Power Engineering
    JO  - International Journal of Energy and Power Engineering
    SP  - 113
    EP  - 120
    PB  - Science Publishing Group
    SN  - 2326-960X
    UR  - https://doi.org/10.11648/j.ijepe.20130203.15
    AB  - 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).
    VL  - 2
    IS  - 3
    ER  - 

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Author Information
  • Joint Stock Company “State Scientific Centre Research Institute of Atomic Reactors”, JSC “SSC RIAR”, Dimitrovgrad, 433510, Russia

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