2018Journal of Physics Conference SeriesOpen access

High-flux lead reactors with average neutron energies up to 1 MeV

G.L. Khorasanov

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Abstract

The paper is devoted to the physics and technology of special nuclear reactor operating on hard neutrons. As is known, a fast neutron spectrum is realized in sodium fast reactors (SFR) at neutron flux densities up to 8⋅10 15 neutrons / cm 2 ⋅ s. In SFRs the coolant and fuel limit the average neutron energy by a value of not more than 0.5 MeV, with a relatively small fraction,15%, of hard neutrons, E n >0.8 MeV. Future high-flux reactors on hard neutrons, with an average neutron energy up to 1 MeV and neutron flux densities on the order of (3-5)⋅10 15 neutrons / cm 2 ⋅s, may be constructed and claimed in the medium term as multipurpose reactors that combine the functions of reactors - transmutators of minor actinides (MA), as well as isotope and research reactors. The requirements for obtaining a hard neutron spectrum in the core of the reactor lead to the need to use nuclear fuel and a coolant that slow moderate neutrons. Metallic fuel should be used as a fuel, and as a coolant - natural lead, whose isotopic composition accounts for the fraction of the slow-moderating 208 Pb isotope a value of 52.3%. An even more harder neutron spectrum can be obtained in the case of using a coolant based on enriched at gas centrifuges 208 Pb or radiogenic 208 Pb extracted from lead-rich thorium ores. The next condition leading to a hard neutron spectrum is the small dimensions of core, D × H ≈ 0.5 × 0.5 meters, in which the initial neutron fission spectra of 235 U, 239 Pu, 241 Pu are not strongly changed. This requirement means that reactors on hard neutrons should be classified as small power or research reactors, within which their thermal capacity does not exceed a value of the order of 200-300 MW.

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The paper is devoted to the physics and technology of special nuclear reactor operating on hard neutrons. As is known, a fast neutron spectrum is realized in sodium fast reactors (SFR) at neutron flux densities up to 8⋅10 15 neutrons / cm 2 ⋅ s. In SFRs the coolant and fuel limit the average neutron energy by a value of not more than 0.5 MeV, with a relatively small fraction,15%, of hard neutrons, E n >0.8 MeV. Future high-flux reactors on hard neutrons, with an average neutron energy up to 1 MeV and neutron flux densities on the order of (3-5)⋅10 15 neutrons / cm 2 ⋅s, may be constructed and claimed in the medium term as multipurpose reactors that combine the functions of reactors - transmutators of minor actinides (MA), as well as isotope and research reactors. The requirements for obtaining a hard neutron spectrum in the core of the reactor lead to the need to use nuclear fuel and a coolant that slow moderate neutrons. Metallic fuel should be used as a fuel, and as a coolant - natural lead, whose isotopic composition accounts for the fraction of the slow-moderating 208 Pb isotope a value of 52.3%. An even more harder neutron spectrum can be obtained in the case of using a coolant based on enriched at gas centrifuges 208 Pb or radiogenic 208 Pb extracted from lead-rich thorium ores. The next condition leading to a hard neutron spectrum is the small dimensions of core, D × H ≈ 0.5 × 0.5 meters, in which the initial neutron fission spectra of 235 U, 239 Pu, 241 Pu are not strongly changed. This requirement means that reactors on hard neutrons should be classified as small power or research reactors, within which their thermal capacity does not exceed a value of the order of 200-300 MW.

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Available abstract

The paper is devoted to the physics and technology of special nuclear reactor operating on hard neutrons. As is known, a fast neutron spectrum is realized in sodium fast reactors (SFR) at neutron flux densities up to 8⋅10 15 neutrons / cm 2 ⋅ s. In SFRs the coolant and fuel limit the average neutron energy by a value of not more than 0.5 MeV, with a relatively small fraction,15%, of hard neutrons, E n >0.8 MeV. Future high-flux reactors on hard neutrons, with an average neutron energy up to 1 MeV and neutron flux densities on the order of (3-5)⋅10 15 neutrons / cm 2 ⋅s, may be constructed and claimed in the medium term as multipurpose reactors that combine the functions of reactors - transmutators of minor actinides (MA), as well as isotope and research reactors. The requirements for obtaining a hard neutron spectrum in the core of the reactor lead to the need to use nuclear fuel and a coolant that slow moderate neutrons. Metallic fuel should be used as a fuel, and as a coolant - natural lead, whose isotopic composition accounts for the fraction of the slow-moderating 208 Pb isotope a value of 52.3%. An even more harder neutron spectrum can be obtained in the case of using a coolant based on enriched at gas centrifuges 208 Pb or radiogenic 208 Pb extracted from lead-rich thorium ores. The next condition leading to a hard neutron spectrum is the small dimensions of core, D × H ≈ 0.5 × 0.5 meters, in which the initial neutron fission spectra of 235 U, 239 Pu, 241 Pu are not strongly changed. This requirement means that reactors on hard neutrons should be classified as small power or research reactors, within which their thermal capacity does not exceed a value of the order of 200-300 MW.

Key concepts: Neutron flux, Neutron, Neutron poison, Neutron cross section, Coolant, Neutron moderator, Nuclear physics, Nuclear reactor core

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