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THE STATUS AND PROSPECT OF DUPIC FUEL TECHNOLOGY  

Yang Myung-Seung (Korea Atomic Energy Research Institute)
Choi Hang-Bok (Korea Atomic Energy Research Institute)
Jeong Chang-Joon (Korea Atomic Energy Research Institute)
Song Kee-Chan (Korea Atomic Energy Research Institute)
Lee Jung-Won (Korea Atomic Energy Research Institute)
Park Geun-Il (Korea Atomic Energy Research Institute)
Kim Ho-Dong (Korea Atomic Energy Research Institute)
Ko Won-Il (Korea Atomic Energy Research Institute)
Park Jang-Jin (Korea Atomic Energy Research Institute)
Kim Ki-Ho (Korea Atomic Energy Research Institute)
Lee Ho-Hee (Korea Atomic Energy Research Institute)
Park Joo-Hwan (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.38, no.4, 2006 , pp. 359-374 More about this Journal
Abstract
Since 1991, Korea, Canada and United States have performed the direct use of spent pressurized water reactor (PWR) fuel in the Canada deuterium uranium (CANDU) reactors (DUPIC) fuel development project. Unlike the Tandem fuel cycle, which requires a wet reprocessing, the DUPIC fuel technology can directly refabricate CANDU fuels from the PWR spent fuel and, therefore, is recognized as a highly proliferation-resistant fuel cycle technology, which can be adopted even in non-proliferation treaty countries. The Korea Atomic Energy Research Institute (KAERI) has fabricated DUPIC fuel elements in a laboratory-scale remote fuel fabrication facility. KAERI has demonstrated the fuel performance in the research reactor, and has confirmed the operational feasibility and safety of a CANDU reactor loaded with the DUPIC fuel using conventional design and analysis tools, which will be the foundation of the future practical and commercial uses of DUPIC fuel.
Keywords
DUPIC; Proliferation-Resistance; OREOX; Compatibility; Economics; Safeguards;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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1 H. Choi and G.H. Roh, 'Benchmarking MCNP and WIMS/RFSP Against Measurement Data ? I: Deuterium Critical Assembly,' Nucl. Sci. Eng., 146, 188 (2004)   DOI
2 I.E. Oldaker, 'Fuel Design Manual for CANDU-6 Reactors,' DM-XX-37000-001, Atomic Energy of Canada Limited (1989)
3 D.C. Groeneveld, L.K.H. Leung, Y. Guo, A. Vasic, M.E. Nakla, S.W. Peng, J. Yang and S.C. Cheng, 'Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future,' Nuclear Technology, 152, 87 (2005)
4 J.B. Slater and C.S. Rim, 'AECL-KAERI Joint Research Program TANDEM Fuel Cycles,' CRNL-2722, Chalk River Nuclear Laboratories (1984)
5 J.H. Ha, W.I. Ko, H.D. Kim, D.Y. Song and S.Y. Lee, 'The Development of a Neutron Multiplicity Counter System for the Nuclear Material Accounting and Safeguards in KAERI,' Journal of Nuclear Science and Technology, Supplement 4, 381 (2004)   DOI
6 H.D. Kim, H.R. Cha, W.I. Ko, D.Y. Song, H.Y. Kang, D.Y. Kim, J.S. Hong, M.S. Yang and H.O. Menlove., 'Technology Development on DUPIC Safeguards System,' Proc. of 41st Institute of Nuclear Material Management Annual Meeting, New Orleans, USA, July 16-20, 2000
7 K.K.S. Pillay, H.O. Menlove and R.R. Picard, 'Safeguardability of Direct Use of Spent PWR Fuels in CANDU Reactors,' LA-12432-MS, Los Alamos National Laboratory (1992)
8 H.D. Kim and W.I. Ko, 'Comparison Study on Plutonium Inventory and Self-Protecting of DUPIC Fuel Cycle,' Proc.of 45th Institute of Nuclear Material Management Annual Meeting, Orlando, USA, July 18-21, 2004
9 J.V. Donnelly, 'WIMS-CRNL: A User's Manual for the Chalk River Version of WIMS,' AECL-8955, Atomic Energy of Canada Limited (1986)
10 Y. Hachiya and H. Hatakenaka, 'Neutron Behavior in Cluster-Type Fuel Lattices, (I) Experimental Method and Results,' Journal of Nuclear Science and Technology, 9, 629 (1972)   DOI
11 Y. Hachiya, N. Fukumura, A. Nishi, K. Iijima and H. Sakata, 'Lattice Parameter Measurements on Cluster-Type Fuel for Advanced Thermal Reactor,' Journal of Nuclear Science and Technology, 13, 618 (1976)   DOI   ScienceOn
12 The Economics of the Nuclear Fuel Cycle, Organization for Economic Cooperation and Development/Nuclear Energy Agency (1993)
13 W.I. Ko, H. Choi and M.S. Yang, 'Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - IV: DUPIC Fuel Cycle Cost,' Nuclear Technology, 134, 167 (2001)   DOI
14 H. Choi, W.I. Ko, M.S. Yang, I. Namgung and B.G. Na, 'Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - II: DUPIC Fuel-Handling Cost,' Nuclear Technology, 134, 130 (2001)   DOI
15 W.I. Ko, H. Choi, G.H. Roh and M.S. Yang, 'Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - III: Spent DUPIC Fuel Disposal Cost,' Nuclear Technology, 134, 149 (2001)   DOI
16 C.J. Jeong and H. Choi, 'Regional Overpower Protection System Analysis for the Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC),' IEEE Transactions on Nuclear Science, 52, 450 (2005)   DOI   ScienceOn
17 B.N. Hanna, 'CATHENA: A Thermal-hydraulic Code for CANDU Analysis,' Nuclear Engineering and Design, 180, 113 (1998)   DOI   ScienceOn
18 M.F. Lightstone, 'NUCIRC-MOD1.505 Users Manual,' TTR-516, Atomic Energy of Canada Limited (1993)
19 L.K.H. Leung, 'Critical Heat Flux for Heavy Water,' ARDTD-243, Atomic Energy of Canada Limited (1996)
20 J. Pitre, 'ROVER-F Manual,' TTR-605 (Rev. 1), Atomic Energy of Canada Limited (1999)
21 D.H. Kim, H. Choi, W.S. Yang and J.K. Kim, 'Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) ? I: Deterministic Analysis,' Nucl. Sci. Eng., 137, 23 (2001)   DOI
22 H. Choi, 'Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) ? II: Statistical Analysis,' Nucl. Sci. Eng., 137, 38 (2001)   DOI
23 C.J. Jeong and H. Choi, 'Instability Analysis on Xenon Spatial Oscillation in a CANDU-6 Reactor with DUPIC Fuel,' Annals of Nuclear Energy, 27, 887 (2000)   DOI   ScienceOn
24 H. Choi, B.W. Rhee and H. Park, 'Burnable Dysprosium for Low Void Reactivity Fuel,' Proc. of Am. Nucl. Soc. Topical Mtg - Advances in Nuclear Fuel Management II, Myrtle Beach, USA, March 23-26, 1997
25 C.J. Jeong and H. Choi, 'Compatibility Analysis on Existing Reactivity Devices in CANDU 6 Reactors for DUPIC Fuel Cycle,' Nucl. Sci. Eng., 134, 265 (2000)   DOI
26 'Final Safety Analysis Report: Wolsong NPP Unit No. 1, Vol. 2,' Korea Electric Power Company (1989)
27 H. Choi, J.W. Choi and M.S. Yang, 'Composition Adjustment on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU,' Nucl. Sci. Eng., 131, 62 (1999)   DOI
28 D.A. Jenkins and B. Rouben, 'Reactor Fuelling Simulation Program - RFSP: User's Manual for Microcomputer Version', TTR-321, Atomic Energy of Canada Limited (1993)
29 H. Choi, B.W. Rhee and H.S. Park, 'Physics Study on Direct Use of Spent PWR Fuel in CANDU (DUPIC),' Nucl. Sci. Eng., 126, 80 (1997)   DOI
30 M.S. Yang, Y.W. Lee. K.K. Bae and S.H. Na, 'Conceptual Study on the DUPIC Fuel Manufacturing Technology,' Proc. Int. Conf. and Technology Exhibition on Future Nuclear System, GLOBAL'93, Seattle, USA, Sept. 12-17, 1993
31 D.G. Martin, 'The Thermal Expansion of Solid $UO_2$ and (U,Pu) Mixed Oxides ? A Review and Recommendations,' J. Nuclear Material, 152, 94 (1988)   DOI   ScienceOn
32 J.K. Fink, 'Thermophysical Properties of Uranium Dioxide,' J. Nuclear Material, 279, 1 (2000)   DOI   ScienceOn
33 H.C. Suk, W. Hwang, B.G. Kim, K.S. Sim, Y.H. Heo, T.S. Byun and G.S. Park, 'ELESTRES.M11K Program User's Manual and Description,' KAERI/TR-320/92, Korea Atomic Energy Research Institute (1992)
34 H. Choi, W.I. Ko and M.S. Yang, 'Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors ? I: DUPIC Fuel Fabrication Cost,' Nuclear Technology, 134, 110 (2001)   DOI
35 K.C. Song, K.H. Kang, C.J. Park and M.S. Yang, 'Estimation of the Irradiation Behavior of DUPIC Fuel at HANARO,' Proc. Int. Symposium on Research Reactor and Neutron Science, Daejeon, Korea, April 10-12, 2005
36 I.J. Hastings, 'Structures in Irradiated $UO_2$ Fuel from Canadian Reactors,' CRNL-2494-4, Atomic Energy of Canada Limited (1984)
37 'Design Manual: CANDU 6 Generating Station Physics Design Manual', 86-03310- DM000, Rev. 1, Atomic Energy of Canada Limited (1995)
38 J.S. Lee, K.C. Song, M.S. Yang, K.S. Chun, B.W. Rhee, J.S. Hong, H.S. Park, C.S. Rim and H. Keil, 'Research and Development Program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors),' Proc. Int. Conf. and Technology Exhibition on Future Nuclear System, GLOBAL'93, Seattle, USA, Sept. 12-17, 1993