Authors & Affiliations
Bikeev A.S., Daichenkova Yu.S., Kalugin M.A., Oleynik D.S., Shkarovsky D.A.
National Research Centre "Kurchatov Institute", Moscow, Russia
Bikeev A.S. – Head of Software Laboratory, National Research Center "Kurchatov Institute".
Kalugin M.A. – Scientific Director of the Kurchatov Nuclear Power Complex, Dr. Sci. (Tech.), National Research Center "Kurchatov Institute".
Oleynik D.S. – Head of Audit Laboratory, National Research Center "Kurchatov Institute".
Shkarovsky D.A. – Head of the Division of Benchmark Calculations of Nuclear Reactors, Cand. Sci. (Tech.), National Research Center "Kurchatov Institute".
In recent years, new approaches have been developed to ensure radiation safety during carting spent nuclear fuel from nuclear power plants with VVER-1000 and VVER-1200 reactors, because the height of the fuel assembly and the initial enrichment of fuel have increased; operating modes of reactors have changed and average burnup in fuel assemblies has increased; new requirements about two safety barriers and prohibition on using liquid neutron protection has appeared. The new generation transport container is designed to cart 18 spent fuel assemblies of VVER-1000 and VVER 1200 reactors to long-term storage.
The main objective of the work is development and testing of the full-scale mathematical model of the new generation transport container for analysis of radiation safety using the Monte Carlo method, as well as performing numerical studies on the selection of optimal non-analog modeling parameters. Using the simple iteration method, the optimal values of the splitting surfaces for the non-analog modeling method “weight window” were determined.
The developed three-dimensional highly detailed model makes it possible to take into account the contribution to the equivalent dose rate from ionizing radiation sources in the top and bottom nozzles, reduce the number of conservative approximations, and, thus, increase the accuracy of radiation safety analysis. Increasing the accuracy of calculating the equivalent dose rate on the surface of the transport container may make it possible to cart spent fuel assemblies with a greater burnup.
MCU-PD, Monte Carlo method, computer simulation, spent nuclear fuel, radiation safety, transport container
1. Gilev Yu.A. Atomic expert: informational and analytical publication, supplement to the scientific journal Atomic Energy, 2017, no. 9 (60), pp. 8–13.
2. Alekseev N.I., Bol'shagin S.N., Gomin E.A., et. al. Status MCU-5 [The Status of the MCU-5]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov - Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2011, no. 4, pp. 5–23.
3. Kalugin M.A., Oleynik D.S., Shkarovsky D.A. Overview of the MCU Monte Carlo software package. Annals of Nuclear Energy, 2015, vol. 82, pp. 54–62.
4. Ford K. World of Elementary Particles. 1st ed. Blaisdell Publishing Co, 1963.
5. Emmett M.B. Calculational Benchmark Problems for VVER-1000 Reactor. ORNL/TM-1999/207,pp. 110.
6. NRB-99-2009. Radiation Safety Standards. Sanitary rules and regulations SanPiN 220.127.116.113-09. Noscow, Standart Publ., 2009.
7. Wagner J.C. Acceleration of Monte Carlo shielding calculations with an automated variance reduction technique and parallel processing. Cand. sci. diss. The Pennsylvania State University, Nuclear Engineering Dept. 1997.
8. Egorov Yu.A. Fundamentals of radiation safety of nuclear power plants. Moscow, Energoizdat Publ., 1982. 272 p. (In Rassian).
9. Center for collective use "Complex of modeling and data processing of mega-class research installations" NRC "Kurchatov Institute". Available at: http://ckp.nrcki.ru (accessed 12.09.2019).
10. Gusev N.G., Klimanov V.A., Mashkovich V.P., Suvorov A.P. Protection against ionizing radiation. Vol. 2. Physical fundamentals of protection against radiation. Moscow, Energoatomizdat Publ., 1989. (In Rassian).