Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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PROLONGATION OF THE BOR-60 REACTOR OPERATION

  • IZHUTOV, ALEXEY L. (JSC SSC RIAR) ;
  • KRASHENINNIKOV, YURI M. (JSC SSC RIAR) ;
  • ZHEMKOV, IGOR Y. (JSC SSC RIAR) ;
  • VARIVTSEV, ARTEM V. (JSC SSC RIAR) ;
  • NABOISHCHIKOV, YURI V. (JSC SSC RIAR) ;
  • NEUSTROEV, VICTOR S. (JSC SSC RIAR) ;
  • SHAMARDIN, VALENTIN K. (JSC SSC RIAR)
  • Received : 2015.02.16
  • Accepted : 2015.02.26
  • Published : 2015.04.25
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Abstract

The fast neutron reactor BOR-60 is one of the key experimental facilities worldwide to perform large-scale tests of fuel, absorbing, and structural materials for advanced reactors. The BOR-60 reactor was put into operation in December 1969, and by the end of 2014 it had been operating on power for ~265,000 hours. BOR-60 still demonstrates potential capabilities to extend the lifetime of sodium-cooled fast reactors. The BOR-60 lifetime should have expired at the end of 2014. Over the past few years, a great scope of work has been performed to justify the possibility of extending its lifetime. The work included inspection of the equipment conditions, calculations and experimental research on operating parameters and the conditions of nonremovable components, investigation of the structural material samples after their long-term operation under irradiation, etc. Based on the results of the work performed, the residual lifetime was evaluated and the reactor operator made a decision to extend the lifetime period of the BOR-60 reactor. After considering both a set of documents about the reactor conditions and the positive decision of independent experts, the Regulatory Authority of the Russian Federation extended the BOR-60 operating license up to 2020.

Keywords

References

  1. A.L. Izhutov, I.Y. Zhemkov, V.S. Neustroev, A.S. Korolkov, Yu. M. Krasheninnikov, M.N. Svyatkin, T.M. Bulanova, A.V. Povstyanko, Prolongation of the BOR-60 Reactor Operation, RRFM-2010 conference, March 2010. Marrakech, Morocco.
  2. International Atomic Energy Agency, Management of Research Reactor Ageing, IAEA-TECDOC-792, IAEA, Vienna, 1995.
  3. E.A. Gomin, M.I. Gurevich, L.V. Mayorov, S.V, Marin Description of Application and Instruction for the User of the MCU-RFFI Calculation Program of the Neutron-physical Characteristics of Nuclear Reactors by the Monte Carlo Method, Preprint IAE-5837/5, Kurchatov Institute, Russia, Moscow, 1994.
  4. A.V. Varivtsev, I.Y. Zhemkov, Improved method for calculating the radiation heat generation in the BOR-60 reactor, Phys. At. Nucl. 77 (14) (2014) 1664-1670. https://doi.org/10.1134/S1063778814140087
  5. J.E. Flinn, T.A. Kendfield, Neutron Swelling Observation on Austenitic Stainless Steels Irradiated in EBR-II, Proceedings of the Workshop on Correlation of Neutron and Charged Particle Damage, Oak Ridge, TN, USA, June 8-10, 1976.
  6. V.S. Neustroev, S.V. Belozerov, T.M. Bulanova, A.V. Varivtsev, I.Y. Zhemkov, A.A. Karsakov, E.I. Makarov, A.V. Obukhov, V.S. Slezko, Material Science Study on the Bar of the Safety Rod AR2 Actuator after -32 Year Operation at a High Temperature in the BOR-60 Reactor, The X Russian Conference on Reactor Material Science: Collected papers, SSC RIAR JSC, Dimitrovgrad, 2013, pp. 647-664.
  7. A.A. Sorokin, B.Z. Margolin, I.P. Kursevich, A.J. Minkin, V.S. Neustroev, Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors, J. Nucl. Mater. (2014) 373-384.
  8. A.V. Varivtsev, I.Y. Zhemkov, Specifics of calculation of heat rate in oxide nuclear fuel during tests in reactor BOR-60. Proceedings of Universities, Nucl. Power 4 (2014) 52-59.

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