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NSR database version of May 10, 2024.

Search: Author = G.G.Komyshev

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2018SH35      At.Energ. 124, 364 (2018)

E.P.Shabalin, V.L.Aksenov, G.G.Komyshev, A.D.Rogov

Neptunium-Based High-Flux Pulsed Research Reactor

NUCLEAR REACTIONS ²³⁷Np, ²³⁸Pu(n, F), E thermal; analyzed available data; deduced The use of neptunium as nuclear fuel for a pulsed neutron source with high thermal neutron flux density both in the variant of a periodic pulse reactor as well as a multiplying neutron generating target of a proton accelerator is preferable to plutonium.

doi: 10.1007/s10512-018-0424-3
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