- Volume 47 Issue 1
DOI QR Code
RECYCLING OPTION SEARCH FOR A 600-MWE SODIUM-COOLED TRANSMUTATION FAST REACTOR
- LEE, YONG KYO (Department of Nuclear Engineering, Kyung Hee University) ;
- KIM, MYUNG HYUN (Department of Nuclear Engineering, Kyung Hee University)
- Received : 2013.12.12
- Accepted : 2014.11.17
- Published : 2015.02.25
Four recycling scenarios involving pyroprocessing of spent fuel (SF) have been investigated for a 600-MWe transmutation sodium-cooled fast reactor (SFR), KALIMER. Performance evaluation was done with code system REBUS connected with TRANSX and TWODANT. Scenario Number 1 is the pyroprocessing of Canada deuterium uranium (CANDU) SF. Because the recycling of CANDU SF does not have any safety problems, the CANDU-Pyro-SFR system will be possible if the pyroprocessing capacity is large enough. Scenario Number 2 is a feasibility test of feed SF from a pressurized water reactor PWR. Thefsensitivity of cooling time before prior to pyro-processing was studied. As the cooling time sensitivity of cooling time before prior to pyro-processing was studied. As the cooling time increases, excess reactivity at the beginning of the equilibrium cycle (BOEC) decreases, thereby creating advantageous reactivity control and improving the transmutation performance of minor actinides. Scenario Number 3 is a case study for various levels of recovery factors of transuranic isotopes (TRUs). If long-lived fission products can be separated during pyroprocessing, the waste that is not recovered is classified as low- and intermediate-level waste, and it is sufficient to be disposed of in an underground site due to very low-heat-generation rate when the waste cooling time becomes >300 years at a TRU recovery factor of 99.9%. Scenario Number 4 is a case study for the recovery factor of rare earth (RE) isotopes. The RE isotope recovery factor should be lowered to
Grant : 개방형 원자로실험 과정 및 단기 비교과 훈련과정 운영
- D. Rochman, A.J. Koning, D.F. Da Cruz, Uncertainties for the KALIMER sodium fast reactor: void reactivity coefficient, keff, beff, depletion and radiotoxicity, Journal of Nuclear Science and Technology 48 (2011) 1193e1205. https://doi.org/10.1080/18811248.2011.9711807
- Y.I. Kim, D. Lee, S.H. Seong, Y.B. Lee, Y.I. Kim, D.H. Hahn, K.H. Moon, Establishment of Advanced SFR Concepts, Rep. No. KAERI/TR-4063/2010, Korea Atomic Energy Research Institute, Daejeon, Korea, 2010.
- G.T. Kim, Y.G. Yun, M.H. Bae, J.H. Song, C.U. Heo, C.Y. Jin, Development of Specific Regulatory Requirements and Guides for Sodium-Cooled Fast Reactors, Rep. No. KINS/RR-896, Korea Institute of Nuclear Safety, Daejeon, Korea, 2011.
- J.Y. Lim, M.H. Kim, A new LFR design concept for effective TRU transmutation, Progress in Nuclear Energy 49 (2007) 230e245. https://doi.org/10.1016/j.pnucene.2006.12.004
- W.S. Yang, Fast reactor physics and computational methods, Nuclear Engineering and Technology 44 (2012) 177e198. https://doi.org/10.5516/NET.01.2012.504
- R.E. MacFarlane, TRANSX 2: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes, Rep. No. LA-12312-MS, Los Alamos National Laboratory, Los Alamos, NM, 1992.
- R.E. Alcouffe, DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System, Rep. No. LA-12969-M, Los Alamos National Laboratory, Los Alamos, NM, 1995.
- B.J. Toppel, A User's Guide for the REBUS-3 Fuel Cycle Analysis Capability, Rep. No. ANL-83-2, Argonne National Laboratory, Argonne, IL, 1983.
- C. Coquelet-Pascal, M. Meyer, R. Girieud, M. Tiphine, R. Eschbach, C. Chabert, C. Garzenne, P. Barbrault, B. Gannaz, L. Van Den Durpel, D. Favet, M. Caron-Charles, B. Carlier, J.-C. Lefevre, Scenarios for fast reactors deployment with plutonium recycling, in: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), 2013.