EDN: UCTWXQ
Authors & Affiliations
Belov A.A., Bereznev V.P., Blokhina G.S., Koltashev D.A., Shurygin R.E.
Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
Belov А.А. – Senior Researcher.
Bereznev V.P. – Researcher, Cand. Sci. (Tech.).
Blokhina G.S. – Engineer .
Koltashev D.A. – Head of the Reactor Physics Laboratory, Cand. Sci. (Tech.).
Shurygin R.E. – Engineer. Contacts: 52, Bolshaya Tulskaya St., Moscow, Russia, 115191. Tel.: +7 (495) 955-23-96; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
The article considers some calculation results using the MCU-FR code to confirm the radiation safety of a spent nuclear fuel (SNF) storage facility for a lead-cooled reactor. Three options of SNF storage facility arrangement and two options of storage cask with various SNF assemblies placement were considered. Irradiated fuel and activated steel of the fuel assembly were considered as a radiation source in the calculations. Based on the simulation results, the ambient dose equivalent rate was estimated inside and outside the SNF storage facility (up to 300 meters), and a two-dimensional distribution of the ambient dose equivalent rate at the level height of 225 cm from the base of the cask (the middle of the fuel part of the fuel rod) in the calculation model. The results of methodological calculations with detailed and simplified storage cask models were analyzed, which showed the conservativeness of the ambient dose equivalent rate estimate in a model with simplified geometry. The distance from the SNF storage facility center at which the ambient dose equivalent rate does not exceed 1.2 μSv/h has been determined. It is shown that the maximum value of ambient dose equivalent rate is achieved in the variant of the SNF storage facility in the form of an open area, SNF assemblies with loss of neutron protection. The main contribution to ambient dose equivalent rate is made by neutron radiation.
Keywords
radiation safety, spent nuclear fuel storage facility, storage cask, spent fuel assemblies, ambient dose equivalent rate, MCU-FR, radiation sources, visualization
Article Text (PDF, in Russian)
References
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UDC 621.039.51...17
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:7
