Neutron induced fission of ²³⁷Np – status, challenges and opportunities

¹ Joint Institute for Nuclear Physics, 141980 Dubna, Moscow region, Russia
² Institute for Nuclear Research and Nuclear Energy of BAS, 1784 Sofia, Bulgaria
³ JSC “SSC-RF-IPPE”, 249033 Obninsk, Kaluga region, Russia
⁴ NRC “Kurchatov Institute”-PNPI, 188300 Gatchina, Leningrad region, Russia
⁵ European Commission, Joint Research Centre, Directorate G, 2440 Geel, Belgium
⁶ ELI-NP/IFIN-HH, 077125 Bucharest-Magurele, Romania

^* e-mail: ivan.n.ruskov@gmail.com

Published online: 6 March 2018

Abstract

Nowadays, there is an increased interest in a complete study of the neutron-induced fission of ²³⁷Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. ²³⁷Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel (“waste”), the incineration of ²³⁷Np becomes an important issue. One scenario for burning of ²³⁷Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmutation and partitioning technology. For testing present fission models, which are at the basis of new generation nuclear reactor developments, highly accurate and detailed neutron-induced nuclear reaction data is needed. However, the EXFOR nuclear database for ²³⁷Np on neutron-induced capture cross-section, σ_γ, and fission cross-section, σ_f, as well as on the characteristics of capture and fission resonance parameters (Γ_γ, Γ_f, σ_oΓ_f, fragments mass-energy yield distributions, multiplicities of neutrons v_n and γ-rays v_γ), has not been updated for decades.