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SM Reactor Core Modification Solving Materials-Science Problems

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Abstract

It is shown that accelerated high-dose irradiation with full instrumentation is useful for radiation materials science research in the high-flux SM research reactor core with an intermediate neutron spectrum. The concept for modifying the core to increase the irradiation volumes in the channels in the fuel part of the core is formulated. The modification is to be done in two stages. First, the reactivity losses due to an increase in the irradiation volumes must be compensated by increasing the uranium load in a fuel element without changing the dimensions and geometry of the element. At the second stage, a new fuel element based on weakly absorbing structural materials will be developed and the specific power release in the core will be increased.

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REFERENCES

  1. A. F. Grachev, V. A. Tsykanov, and V. N. Golovanov, “Research reactors and problems of material science for nuclear engineering and technology,” in: International Conference on “Research Reactors: Science and High Technologies,” Dmitrovgrad, NIIAR (2001), Vol. 1, p. 104.

    Google Scholar 

  2. B. V. Samsonov and V. A. Tsykanov, Reactor Methods of Materials Science, Énergoatomizdat, Moscow (1991).

    Google Scholar 

  3. V. V. Pimenov, Yu. P. Polyakov, and V. I. Sluzhaev, “Calculation of radiation damage and production of gaseous transmutants in metals under irradiation in channels in SM-2, BOR-60, and PBT-6 reactors,” Preprint NIIAR-9 (417) (1980).

  4. V. A. Tsykanov, M. N. Svyatkin, A. V. Klinov, and V. A. Starkov, “Modernization of SM reactor core,” in: International Conference on “Research Reactors: Science and High Technologies,” Dmitrovgrad, NIIAR (2001), Vol. 2, Pt. I, p. 3.

    Google Scholar 

  5. A. V. Klinov, V. A. Kuprienko, V. A. Lebedev, et al., “Study of fuel element characteristics of CM and SMT (SM-PRIMA) fuel assemblies,” in: Proceedings of the 3rd International Topical Meeting: Research Reactor Fuel Management (RRFM), Brugge, March 28–30, 1999.

  6. MCU-RFFI/A Code with DLG/MCUDAT-1.0 Constants Library. Appendix to the Software Certification Certificate No. 61, October 17, 1996, NTTs YaRB Gosatomnadzor Rossii, Moscow (1996).

  7. E. A. Gomin, M. I. Gurevich, L. V. Maiorov, and S. V. Marin, “Description of the application and user instructions for the MCU-RFFI code for Monte Carlo calculation of the neutron-physical characteristics of nuclear reactors,” Preprint IAÉ-5837/5 (1994).

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Tsykanov, V.A., Klinov, A.V., Starkov, V.A. et al. SM Reactor Core Modification Solving Materials-Science Problems. Atomic Energy 93, 713–717 (2002). https://doi.org/10.1023/A:1021763815423

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  • DOI: https://doi.org/10.1023/A:1021763815423

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