Publication: Analytical studies on the potential of 238Pu production in the large-size fast neutron power reactor
Дата
2025
Авторы
Vnukov, R. A.
Rodina, E. A.
Khomyakov, Y. S.
Journal Title
Nuclear Energy and Technology (NUCET)
Journal ISSN
Volume Title
Nuclear Energy and Technology (NUCET)
Издатель
НИЯУ МИФИ
Аннотация
The possibility of obtaining 238Pu in the BN-1200M (about 1,200 MWe) fast neutron power reactor is considered. To obtain products with a purity of 80–85% in terms of 238Pu, options were proposed with installation of irradiation assemblies (IA) with breeding and moderating elements in the radial blanket. Neptunium and americium oxides and their mixtures were considered as target materials of the breeding elements for producing target nuclide. Zirconium hydride was considered as a moderator. The effective density of targets, IA arrangement, target/moderator materials content ratio, and irradiation time were varied. Calculations were made to determine mass and composition of produced plutonium and IA decay heat, as well as IA effect on the global and local pin-to-pin power profile in the standard fuel assemblies of the reactor core.
When using targets made of neptunium oxide, options were effective only at an effective density of approximately 1.1 g/cm³ were only effective because of self-shielding effect. Irradiation during 4–5 years ensures required 80% purity of 238Pu with target purity in terms of 236Pu within 2 ppm. When using Am, 236Pu purity is also ensured, but 238Pu fraction is somewhat lower than 80% due to the higher fraction of 242Pu. The use of Am and Np mixture makes it possible to reduce the fraction of 236Pu and prevent high accumulation of 242Pu, but in this case 242Cm accumulation should be taken into account, and appropriate time period for its decay heat reduction should be chosen.
Описание
Ключевые слова
Zirconium hydride , Americium , Neptunium , Moderator element , Irradiation device , BN-1200 fast reactor , Radioisotope products
Цитирование
Vnukov RA, Rodina EA, Khomyakov YS (2025) Analytical studies on the potential of 238Pu production in the large-size fast neutron power reactor. Nuclear Energy and Technology 11(4): 293–299. https://doi.org/10.3897/nucet.11.170677