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Investigation of Thermal and Epithermal Neutron Flux Distributions in Universal Nuclear Icebreaker Fuel Assemblies

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The results of experimental investigations of the spatial and energy distributions of the thermal and epithermal neutrons in a cassette fuel assembly, similar in design to that developed for the RITM-200 reactor core in the universal nuclear icebreaker, are presented. The measurements were performed using activation detectors with the isotopes 63Cu, 55Mn, and 197Au. It is shown that the structural nonuniformities of the fuel assembly (central water cavity, reactivity compensation system absorbing rod, strongly screened rods with consumable absorber) create significant thermal neutron flux nonuniformity over the cross-section of a fuel assembly. The flux distribution of epithermal neutrons with energy >0.4 eV is almost uniform. The experimental data are supported by calculations.

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References

  1. D. L. Zverev, A. N. Pakhomov, V. I. Polunichev, et al., “Next-generation reactor unit RITM-200 for an advanced nuclear icebreaker,” At. Energ., 113, No. 6, 323–328 (2012).

    Google Scholar 

  2. O. B. Samoilov, D. G. Preobrazhenskii, O. A. Morozov, et al., “Cores of floating NPP – state and prospects for development,” in: Floating NPP Safety and Cost-Effectiveness Validation, Prospects for Use in Russia and Abroad: Proc. Interdbranch Sci. Appl. Conf., PATEX-2008, Nizhnii Novgorod (2008), p. 27.

  3. O. B. Samoilov, O. A. Morozov, V. A. Panov, et al., “Development of the design of a core for the KLT-40S reactor for PATES and enhanced power service life,” in: Next-Generation Nuclear Fuel for NPP. Results of Development Work, Experimental Operation, and Direction of Development: Proc. Sci. Techn. Conf., Moscow (2012), p. 72.

  4. V. I. Bryzgalov, E. A. Gomin, A. M. Demidov, et al., “Comparison of computational data (MCU code) and experiments (reactor F-1) in evaluations of the parameters of neutron spectra measured using activation detectors,” Vopr. At. Nauki Tekhn. Ser. Fiz. Yad. Reakt., No. 4, 61–67 (2002).

  5. V. I. Bryzgalov, A. M. Demidov, V. S. Dikarev, et al., “Use of unified composite detectors for measuring neutron spectra,” At. Energ., 104, No, 4, 227–233 (2008).

    Article  Google Scholar 

  6. A. V. Batulin, B. M. Ershov, Yu. V. Konovalov, et al., “Development of fuel elements for floating powergenerating units and low-capacity nuclear power plants,” in: Floating NPP Safety and Cost-Effectiveness Validation, Prospects for Use in Russia and Abroad: Proc. Interdbranch Sci. Appl. Conf., PATEX-2008, Nizhnii Novgorod (2008), p. 28.

  7. E. A. Gomin, “MCU-4 status,” Vopr. At. Nauki Tekhn. Ser. Fiz. Yad. Reakt., No. 1, 6–32 (2006).

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Translated from Atomnaya Énergiya, Vol. 121, No. 6, pp. 307–313, December, 2016.

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Samoilov, O.B., Alekseev, V.I., Galitskikh, V.Y. et al. Investigation of Thermal and Epithermal Neutron Flux Distributions in Universal Nuclear Icebreaker Fuel Assemblies. At Energy 121, 389–396 (2017). https://doi.org/10.1007/s10512-017-0217-0

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  • DOI: https://doi.org/10.1007/s10512-017-0217-0

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