Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel
Irkimbekov R.А. Vurim A.D. Bedenko S.V. Vlaskin G.N. Surayev A.S. Vityuk G.А. Vega-Carrillo H.R.
March 2022Elsevier Ltd
Applied Radiation and Isotopes
2022#181
Safe irradiated nuclear fuel (INF) storage of research reactors is ensured by solving issues of protection against γ-irradiation while the neutron component is usually without consideration due to significantly lower intensity. Regarding the low-enriched composite uranium fuel of the IVG.1M reactor that is characterized by a set of elements with low and mean atomic weight where reaction is possible (α, n), evaluation of the neutron component is an indispensable procedure for ensuring radiation safety INF storage. This research suggests a method for neutron component calculation of radiation properties of fresh and irradiated fuel of the IVG.1M reactor, the α-n-component was evaluated. The research results will be useful when choosing a technology for INF storage and for analysis of feasibility to use neutron irradiation with a purpose to control fuel burnout.
(α, n)-reaction , Dosimetry , Low-enriched uranium nuclear fuel , The IVG.1M research reactor
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Institute of Atomic Energy, National Nuclear Center of Republic of Kazakhstan, Kurchatov, 071100, Kazakhstan
School of Nuclear Science and Engineering, Tomsk Polytechnic University, Tomsk, 634030, Russian Federation
Innovation Technology Centre for the PRORYV Project, Rosatom, 119017, Moscow, Russian Federation
Academic Unit of Nuclear Studies of the Autonomous University of Zacatecas, Zacatecas, 98068, Zac, Mexico
Institute of Atomic Energy
School of Nuclear Science and Engineering
Innovation Technology Centre for the PRORYV Project
Academic Unit of Nuclear Studies of the Autonomous University of Zacatecas
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