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Author Oleg, Shcherbakov ♦ Walter, Furman ♦ Andreas, Oberstedt ♦ Andrei, Goverdovski ♦ Yury, Kopatch ♦ Stephan, Oberstedt ♦ Ivan, Ruskov ♦ Franz-Josef, Hambsch
Source Directory of Open Access Journals (DOAJ)
Content type Text
Publisher EDP Sciences
File Format PDF
Date Created 2018-03-15
Copyright Year ©2018
Language English
Subject Domain (in LCC) QC1-999
Subject Keyword Science ♦ Physics
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, σγ, and fission cross-section, σf, as well as on the characteristics of capture and fission resonance parameters (Γγ, Γf, σoΓf, fragments mass-energy yield distributions, multiplicities of neutrons vn and γ-rays vγ), has not been updated for decades.
ISSN 2100014X
Age Range 18 to 22 years ♦ above 22 year
Educational Use Research
Education Level UG and PG ♦ Career/Technical Study
Learning Resource Type Article
Publisher Date 2018-01-01
e-ISSN 2100014X
Journal EPJ Web of Conferences
Volume Number 169
Starting Page 00021


Source: Directory of Open Access Journals (DOAJ)