Safe Controlled Storage of SVBR-100 Spent Nuclear Fuel in the Extended-Range Future
- 1 JSC “SSC RF-IPPE”, Obninsk, Russia
- 2 JSC “AKME-Engineering”, Moscow, Russia
- 3 JSC “AKME-Engineering”, Moscow, Russia
- 4 JSC “AKME-Engineering”, Moscow, Russia
- 5 JSC “SSC RF-IPPE”, Obninsk, Russia
Abstract
Experience of operating reactor facilities (RF) with lead-bismuth coolant (LBC) has revealed that it is possible to perform safe refueling in short terms if the whole core is replaced and a kit of the special refueling equipment is used. However, comparing with RFs of nuclear submarines (NS), in which at the moment of performance of refueling the residual heat release is small, at RF SVBR-100 in a month after the reactor has been shut down , at the moment of performance of refueling the residual heat release is about 500 kW. Therefore, it is required to place the spent removable unit (SRU) with spent fuel subassemblies (SFSA) into the temporal storage tank (TST) filled with liquid LBC, in which the conditions for coolant natural circulation (NC) and heat removal via the tank vessel to the water cooling system are provided. After the residual heat release has been lowered to the level allowing transportation of the TST with SRU in the transporting-package container (TPC), it is proposed to consider a variant of TPCs transportation to the special site . On that site after the SRU h as been reloaded into the long storage tank (LST) filled with quickly solidifying liquid lead, the TPCs can be stored during the necessary period. Thus, the controlled storage of LSTs is realized during several decades un till the time when SNF reprocessing and NFC closing are becoming economically expedient. On that storage, the four safety barriers are formed on the way of the release of radioactive products into the environment, namely: fuel matrix, fuel element cladding, solid lead and steel casing of the LST.
- Novikova, N.N., Komlev, O.G. and Toshinsky, G.L. (2006) Neutronic and Physical Characteristics of Reactor SVBR-75/100 with Different Types of Fuel. Proceedings of ICAPP’06, Reno, NV, USA, 4-8 June 2006, Paper No. 6355.
- Zrodnikov, A.V., Toshinsky, G.I., Dragunov, Yu.G., Stepanov, V.S., et al. (2006) Nuclear Power Development in Market Conditions with Use of Multi-Purpose Modular Fast Reactors SVBR-75/100. Nuclear Engineering and Design, 236, 1490-1502. https://doi.org/10.1016/j.nucengdes.2006.04.005
- Zrodnikov, A.V., Toshinsky, G.I., Komlev, O.G., et al. (2011) Fuel Cycle for Reactor SVBR-100. Journal of Materials Science and Engineering В, 1, 929-937.
- Report on Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) (2003) Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles, IAEA-TECDOC-1362.
- Klaus Yanberg and Frank fon Hippel (2017) Dry Interim Container Storage of SNF as an Alternative to Its Reprocessing. Journal Atomnaya Strategiya XXI, 127, 6-9. (in Russian)
- Yucca Mountain Science and Engineering Report, Rev. 1. (2002) Executive Summary, U.S. Department of Energy, DOE/RW-0539.
- MIT Report of the Future of the Nuclear Fuel Cycle (2011) An Interdisciplinary MIT Study.
- MIT Report of the Future of Nuclear Power (2003) An Interdisciplinary MIT Study. http://web.mit.edu/nuclearpower/pdf/nuclearpower-full.pdf
- Nuclear Electricity. Uranium Information Center (2000) 6th Edition, Chapter 3.
- Uranium (2007) Resources, Production and Demand. Red Book Reporting. A Joint Report by the OECD Nuclear Energy Agency and the International Atomic Energy Agency (2008), NEA No. 6345.
- Sazonov, V.K., Toshinsky, G.I., Stepanov, V.S., et al. (1998) Technology and Experience of Repair Works and Refuelings for the Nuclear Power Installations with Lead-Bismuth Coolant. Paper in the Book by Georgii Toshinskii, “Lead-Bismuth Cooled Fast Reactors (Collection of Selected Articles and Papers”, LAMBERT Academic Publishing (2017-01-18 ISBN-13: .978-3-330-02561-5)