EDN: UHLZWP
Authors & Affiliations
Kolesov V.V.1, Korobeynikov V.V.2 , Pupko L.P.2
1 Obninsk Institute for Nuclear Power Engineering of the National Research Nuclear University, Obninsk, Russia
2 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Kolesov V.V.1 – Assistant Professor, Dr. Sci. (Phys.-Math.).
Korobeinikov V.V.2 – Chief Researcher, Professor, Dr. Sci. (Phys.-Math.). Contact: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (910) 863-70-98; e-mail: vvkorobeynikov @ippe.ru.
Pupko L.P.2 – Researcher.
Abstract
The article presents the results of studies on the use of minor actinides for the production of 238Pu. The most common starting material for the production of 238Pu in a nuclear reactor is the neptunium isotope 237Np. Traditionally, thermal neutron reactors are used for this purpose. This paper considers an approach to the production of 238Pu based on the irradiation of minor actinides in a fast neutron reactor. Not only 237Np, but also 241Am are studied as starting material. An analysis of the efficiency of 238Pu production using two different schemes is carried out. Their advantages and disadvantages are considered. Three versions of irradiation devices were used for the studies, differing in the amount of moderating material surrounding the fuel assembly with starting materials. The results showed that the presence of a moderator in irradiation devices with 237Np reduces the accumulation of “harmful” 236Pu. Comparison of graphite and zirconium hydride moderators showed higher efficiency of graphite. Using 241Am as a starting material showed a fairly low level of accumulation of “harmful&rdquo. 236Pu even in the absence of a moderator. However, the proportion of 238Pu is lower in the case of using 241Am compared to 237Np.
Keywords
transmutation, minor actinide burnout, spent fuel, radioactivity, biological hazard, spent fuel storage, neutron spectrum, heterogeneity
Article Text (PDF, in Russian)
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UDC 621.039.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 4, 4:12
