The closed on-site fuel cycle of the brest reactors

Orlov, V. V.; Filin, A. I.; Lopatkin, A. V.; Glazov, A.G.; Sukhanov, L. P.; Volk, V. I.; Poluéktov, P. P.; Ustinov, O. A.; Vorontsov, Mikhail; Leontiev, V.F.; Karimov, R.S.

doi:10.1016/j.pnucene.2005.05.017

Cited by 21 publications

(2 citation statements)

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“…For simplicity, let effective fraction of delayed neutrons be the same for all the fast reactor models under consideration here, ( 235 U) = 0.0065. The curves presented in Figure 1 demonstrate dependencies of the reactivity jump required to provide the 2 International Journal of Nuclear Energy power excursion with asymptotic time period (without any feedback effects) in the fourth-generation lead-cooled, fast BREST-type [8] reactor (neutron reflector-50 cm thick natural lead), in thermal VVER-type and CANDU-type reactors as well as in two hypothetical reactors whose prompt neutron lifetimes are equal to 0.01 s and 0.1 s, respectively.…”

Section: Prompt Neutron Lifetime Of Different Reactorsmentioning

confidence: 99%

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

Kulikov

Шмелев

Апсэ

2014

International Journal of Nuclear Energy

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Light materials with small atomic mass (light or heavy water, graphite, and so on) are usually used as a neutron reflector and moderator. The present paper proposes using a new, heavy element as neutron moderator and reflector, namely, “radiogenic lead” with dominant content of isotope208Pb. Radiogenic lead is a stable natural lead. This isotope is characterized by extremely low micro cross-section of radiative neutron capture (~0.23 mb) for thermal neutrons, which is smaller than graphite and deuterium cross-sections. The reflector-converter for a fast reactor core is the structure capable of transforming some part of prompt neutrons leaked from the core into the reflected neutrons with properties similar to those of delayed neutrons, that is, sufficiently large contribution to reactivity at the level of effective fraction of delayed neutrons and relatively long lifetime, comparable with lifetimes of radionuclides-emitters of delayed neutrons. It is evaluated that the use of radiogenic lead makes it possible to slow down the chain fission reaction on prompt neutrons in the fast reactor. This can improve the fast reactor safety and reduce some requirements to the technologies used to fabricate fuel for the fast reactor.

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Section: Prompt Neutron Lifetime Of Different Reactorsmentioning

confidence: 99%

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

Kulikov

Шмелев

Апсэ

2014

International Journal of Nuclear Energy

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“…Some different approaches with multiple-recycle fuel cycles for fast reactors, which could provide radically higher aggregate combustion percentages, should be mentioned here (Orlov et al. 2005; Moiseenko et al. 2012; Ternovykha et al.…”

Section: Introductionmentioning

confidence: 99%

Stellarator–mirror fusion–fission hybrid – a fast route to clean and safe nuclear energy

Moiseenko,

Chernitskiy,

Ågren

et al. 2023

J. Plasma Phys.

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The multiple-recycle fuel cycle for uranium-238 considered here, if practically realized, can bring revolutionary changes in nuclear energy. A full use of uranium-238 implies a practically infinite resource for power generation. Besides the energy, the fuel cycle net output is only fission products, which are co-products rather than waste. For the same amount of energy produced, the amount of fission products is two orders of magnitude less compared with the amount of spent nuclear fuel generated in currently exploited nuclear energy production scenarios. Using the simplest isotope balance model, key features of the multiple-recycle fuel cycle for uranium-238 are investigated. The repetition of this cycle results in smooth transformation of the initial fuel to ‘stationary’ fuel without strong variations in the fractional isotope content. Deficit of delayed neutrons is a threat of the fuel cycle considered as well as other fuel cycles that use plutonium. It has a dramatic impact on reactor controllability and safety. A solution to this threat could be a subcritical nuclear reactor with an external neutron source. In this paper, use of a stellarator–mirror (SM) fusion–fission hybrid for the multiple-recycle fuel cycle for uranium-238 is analysed. A summary of the experimental and theoretical studies on the SM hybrid is given. Preliminary results for principal design of a SM hybrid nuclear reactor for the multiple-recycle fuel cycle for uranium-238 are presented.

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Temperature control characteristics analysis of lead-cooled fast reactor with natural circulation

Yang

Song

Wang

et al. 2016

Annals of Nuclear Energy

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The closed on-site fuel cycle of the brest reactors

Cited by 21 publications

References 0 publications

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

Stellarator–mirror fusion–fission hybrid – a fast route to clean and safe nuclear energy

Temperature control characteristics analysis of lead-cooled fast reactor with natural circulation

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