Browse > Article
http://dx.doi.org/10.1016/j.net.2018.09.007

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor  

Lim, Dong-Won (Department of Mechanical Engineering, University of Suwon)
Lee, Cheol-Woo (Nuclear Data Center, Korea Atomic Energy Research Institute (KAERI))
Lim, Jae-Yong (SFR Reactor Design Division, Korea Atomic Energy Research Institute (KAERI))
Hartanto, Donny (Department of Mechanical and Nuclear Engineering, University of Sharjah)
Publication Information
Nuclear Engineering and Technology / v.51, no.1, 2019 , pp. 284-292 More about this Journal
Abstract
For the continuous operation of a nuclear reactor, burnt fuel needs to be replaced with fresh fuel, where appropriate (ex-vessel) fuel handling is required. Particularly for the Sodium-cooled Fast Reactor (SFR) refueling, its process has unique challenges due to liquid sodium coolant. The ex-vessel spent fuel transportation should concern several design features such as the radiation shielding, decay-heat removal, and inert space separated from air. This paper proposes a new design optimization methodology of cask shielding to transport the spent fuel assembly in a prototype SFR for the first time. The Particle Swarm Optimization (PSO) algorithm had been applied to design trade-offs between shielding and cask weight. The cask is designed as a double-cylinder structure to block an inert sodium region from the air-cooling space. The PSO process yielded the optimum shielding thickness of 26 cm, considering the weight as well. To confirm the shielding performance, the radiation dose of spent fuel removed at its peak burnup and after 1-year cooling was calculated. Two different fuel positions located during transportation were also investigated to consider a functional disorder in a cask drive system. This study concludes the current cask design in normal operations is satisfactory in accordance with regulatory rules.
Keywords
Fuel transfer cask; Radiation shielding; MCNP; Particle Swarm Optimization (PSO); Sodium-cooled Fast Reactor Refueling;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 T. Abram, S. Ion, Generation-IV nuclear power: a review of the state of the science, Energy Pol. 36 (12) (2008) 4323-4330.   DOI
2 J. Rouault, et al., Sodium fast reactor design: fuels, neutronics, thermalhydraulics, structural mechanics and safety, in: Handbook of Nuclear Engineering, Springer, 2010, pp. 2321-2710.
3 Y. Chikazawa, M. Farmer, C. Grandy, Technology gap analysis on sodiumcooled reactor fuel-handling system supporting advanced burner reactor development, Nucl. Technol. 165 (3) (2009) 270-292.   DOI
4 R.T. Klann, B.A. Picker Jr., A conceptual redesign of an inter-building fuel transfer cask, in: Proceedings of 2nd ASME-JSME International Conference on Nuclear Engineering, San Francisco, CA, USA, March 21-24, 1993.
5 B.C. Cerutti, et al., EBR-II fuel handling system, in: Proceedings of Symposium on Progress in Sodium-cooled Fast Reactor Engineering, Monaco, March 23-27, 1970.
6 D. Madden, E. Garrett, Design of the FFTF fuel handling systems bottom loading transfer casks, in: Tech. rep., Aerojet Mfg. Co., Fullerton, Calif.(USA), Westinghouse Hanford Co., Richland, Wash.(USA), 1973.
7 P. Puthiyavinayagam, et al., Development of fast breeder reactor technology in India, Prog. Nucl. Energy 101 (2017) 19-42.   DOI
8 B. Sodhi, et al., Conceptual Design of Core Component Handling System in PFBR, 1996. IAEA-TECDOC-907.
9 N. Kawasaki, et al., Design study for reactor system of fast reactor JSFRconcept of reactor system, in: Proceedings of the ICAPP2015, Nice, France, May 3-6, 2015.
10 F. Dechelette, et al., Study and Evaluation of Innovative Fuel Handling Systems for Sodium-cooled Fast Reactors: Fuel Handling Route Optimization, Science and Technology of Nuclear Installations, 2014. Article ID 254913.
11 Y. Chikazawa, et al., JSFR key technology evaluation on fuel handling system, J. Nucl. Sci. Technol. 51 (4) (2014) 437-447.   DOI
12 J. Yoo, et al., Overall system description and safety characteristics of prototype gen-IV sodium cooled fast reactor in Korea, Nuclear Engineering and Technology 48 (5) (2016) 1059-1070.   DOI
13 R. Eberhart, J. Kennedy, A new optimizer using particle swarm theory, in: Proceedings of the Sixth International Symposium on Micro Machine and Human Science, Nagoya, Japan, October 4-6, 1995.
14 J. Kennedy, Particle swarm optimization, in: Encyclopedia of Machine Learning, Springer, 2011, pp. 760-766.
15 R. l. Perez, K. Behdinan, Particle swarm approach for structural design optimization, Comput. Struct. 85 (19-20) (2007) 1579-1588.   DOI
16 X. Hu, R.C. Eberhart, Y. Shi, Engineering optimization with particle swarm, in: Proceedings of the 2003 IEEE Swarm Intelligence Symposium, Indianapolis, IN, USA, April 26, 2003.
17 M. Asami, K. Sawada, A. Konnai, N. Odano, Application of dose evaluation of the MCNP code for the spent fuel transport cask, Progress of Nuclear Science and Technology 2 (2011) 855-859.   DOI
18 R. Hassan, et al., A comparison of particle swarm optimization and the genetic algorithm, in: 46th AIAA/ASME/ASCE/AHS/ASC Structures, Structural 590 Dynamics and Materials Conference, 2005, p. 1897.
19 D. Pelowitz (Ed.), MCNP6 User's Manual Version 1.0, LA-CP-13-00634, Los Alamos National Laboratory, 2013.
20 J.H. Ko, et al., Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions, Nuclear Engineering and Technology 46 (4) (2014) 547-556.   DOI
21 IAEA, Regulations for the Safe Transport of Radioactive Material, International Atomic Energy Agency, 2012. IAEA Safety Standards No. SSR-6.
22 A.G. Croff, User's Manual for the ORIGEN2 Computer Code, ORNL/TM-7175, Oak Ridge National Laboratory, 1980.
23 US Nuclear Regulatory Commission, NRC Regulations Title 10, Code of Federal Regulations (10 CFR), Part 20-standards for protection against radiation, https://www.nrc.gov/reading-rm/doc-collections/cfr/part020/, page accessed Friday, February 16, 2018.
24 US Nuclear Regulatory Commission, Standard Review Plan for Spent Fuel Dry Storage Facilities: Final Report, 2000. NUREG-1567.
25 Nuclear Safety & Security Commission, Standards for Safe Operation of Radioactive Materials, http://www.law.go.kr, page accessed on Friday, June 1st, 2018.