Autor: |
Ruskov, Ivan, Goverdovski, Andrei, Furman, Walter, Kopatcha, Yury, Shcherbakov, Oleg, Hambsch, Franz-Josef, Oberstedta, Stephan, Oberstedt, Andreas |
Předmět: |
|
Zdroj: |
EPJ Web of Conferences; 2018, Vol. 169, p1-5, 5p |
Abstrakt: |
Nowadays, there is an increased interest in a complete study of the neutroninduced 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,ργ, and fission cross-section, ρf, as well as on the characteristics of capture and fission resonance parameters (Γ;γ, ρf, ρoΓf, fragments mass-energy yield distributions, multiplicities of neutronsνn and γ-rays νγ), has not been updated for decades. [ABSTRACT FROM AUTHOR] |
Databáze: |
Complementary Index |
Externí odkaz: |
|