-
1
-
-
50149093083
-
-
Boczar, P.G. et al., 2002. Thorium Fuel Cycle Studies for CANDU Reactors. IAEA-TECDOC-1319, International Atomic Energy Agency.
-
Boczar, P.G. et al., 2002. Thorium Fuel Cycle Studies for CANDU Reactors. IAEA-TECDOC-1319, International Atomic Energy Agency.
-
-
-
-
2
-
-
50149094879
-
-
Bychkov, A.V. et al., 1997. Fuel cycle of actinide burner-reactor: review of investigations by <> program. In: Proceedings of International Conference on Future Nuclear Systems, Yokohama, Japan, October 5-10, 1997, p. 657.
-
Bychkov, A.V. et al., 1997. Fuel cycle of actinide burner-reactor: review of investigations by <> program. In: Proceedings of International Conference on Future Nuclear Systems, Yokohama, Japan, October 5-10, 1997, p. 657.
-
-
-
-
3
-
-
31744432361
-
A physics study on thorium fuel recycling in a CANDU reactor using dry process technology
-
Choi H., and Park C.J. A physics study on thorium fuel recycling in a CANDU reactor using dry process technology. Nuclear Technology 153 (2006) 132
-
(2006)
Nuclear Technology
, vol.153
, pp. 132
-
-
Choi, H.1
Park, C.J.2
-
4
-
-
50149103969
-
-
Critoph, E. et al., 1976. Prospects for Self-Sufficient Equilibrium Thorium Fuel Cycles in CANDU Reactors. AECL-5501, Atomic Energy of Canada Limited.
-
Critoph, E. et al., 1976. Prospects for Self-Sufficient Equilibrium Thorium Fuel Cycles in CANDU Reactors. AECL-5501, Atomic Energy of Canada Limited.
-
-
-
-
5
-
-
0028452678
-
An evaluation of the development of AIROX-recycled fuel in pressurized water reactors
-
Jahshan S.N., and Mcgreehan T.J. An evaluation of the development of AIROX-recycled fuel in pressurized water reactors. Nuclear Technology 106 (1994) 350
-
(1994)
Nuclear Technology
, vol.106
, pp. 350
-
-
Jahshan, S.N.1
Mcgreehan, T.J.2
-
6
-
-
43849106565
-
Dynamic modeling and analysis of alternative fuel cycle scenarios in Korea
-
Jeong C.J., and Choi H. Dynamic modeling and analysis of alternative fuel cycle scenarios in Korea. Nuclear Engineering and Technology 39 1 (2007) 85
-
(2007)
Nuclear Engineering and Technology
, vol.39
, Issue.1
, pp. 85
-
-
Jeong, C.J.1
Choi, H.2
-
7
-
-
50149101135
-
-
Lee, J.S. et al., 1993. Research and development program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors). In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 733.
-
Lee, J.S. et al., 1993. Research and development program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors). In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 733.
-
-
-
-
8
-
-
50149113520
-
-
Mayoshin, A.A. et al., 1995. Development of UPuO2 vibropac fuel elements capable of operation up to super-high burnups. In: Proceedings of International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, September 11-14, 1995, p. 1417.
-
Mayoshin, A.A. et al., 1995. Development of UPuO2 vibropac fuel elements capable of operation up to super-high burnups. In: Proceedings of International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, September 11-14, 1995, p. 1417.
-
-
-
-
9
-
-
50149094075
-
-
MOCIE (Ministry of Commerce, Industry and Energy), 2004. The Second Basic Electricity Demand and Supply Plan.
-
MOCIE (Ministry of Commerce, Industry and Energy), 2004. The Second Basic Electricity Demand and Supply Plan.
-
-
-
-
10
-
-
34249011213
-
Implementation of a dry fuel cycle model into the DYMOND code
-
Park J.H., et al. Implementation of a dry fuel cycle model into the DYMOND code. Journal of Korean Nuclear Society 36 (2004) 175
-
(2004)
Journal of Korean Nuclear Society
, vol.36
, pp. 175
-
-
Park, J.H.1
-
12
-
-
50149113317
-
-
Skiba, O.V. et al., 1993. Nuclear fuel cycle based on "dry" methods for fuel reprocessing and fuel elements manufacture automated process. In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 934.
-
Skiba, O.V. et al., 1993. Nuclear fuel cycle based on "dry" methods for fuel reprocessing and fuel elements manufacture automated process. In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 934.
-
-
-
-
14
-
-
50149096638
-
-
US Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2001. Generation 4 Roadmap Fuel Cycle Crosscut Group Executive Summary.
-
US Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2001. Generation 4 Roadmap Fuel Cycle Crosscut Group Executive Summary.
-
-
-
-
15
-
-
50149095090
-
-
Yang, M.S. et al., 1993. Conceptual study on the DUPIC fuel manufacturing technology. In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 740.
-
Yang, M.S. et al., 1993. Conceptual study on the DUPIC fuel manufacturing technology. In: Proceedings of International Conference on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, Washington, September 12-17, 1993, p. 740.
-
-
-
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