Perspectives of the thorium fuel cycle

Nuclear Engineering and Design

Volumn 180, Issue 2, 1998, Pages 133-146

  Lung, Michel ^a   Gremm, Otto ^a  

^a NONE

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0001155182     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(97)00296-3     Document Type: Review

References (65)

1. Chidambaram, R., Ganguly, C., 1996. Plutonium and thorium in the Indian nuclear programme. Curr. Sci. 70 (1).
2. Eschbach, E.A., Deonigi, D.E., 1966. Possible optimum use of thorium and uranium employing crossed-progeny fuel cycles. In: Batelle, P.N.L. (Ed.), Second International Symposium on Thorium Fuel Cycle, Gatlinburg, TN, USA.
3. Furukawa, K., Simonenko, V.A. et al., 1997. Thorium cycle implementation through Pu incineration by thorium molten-salt nuclear energy synergetics. In: IAEA Advanced Group Meeting, April, 1997.
4. IAEA, 1997. The status of thorium-based fuel options. Topical Meeting, April, 1997.
5. IAEA, 1994. Consultancy Meeting in Thorium Fuel Cycle, December, 1994.
6. IAEA, 1992. A Fresh look at the Thorium Cycle, Expert Report.
7. IAEA, 1990. Consultancy Meeting on the Use of Thorium-based Fuels, Vienna, Austria.
8. IAEA, 1985. Thorium-based Nuclear Fuels, Current Status and Perspectives, TECDOC 412, Vienna, Austria.
9. IAEA, 1980. INFCE Report, Vienna, Austria.
10. IAEA, 1970. Thorium Fuel Cycle, Bibliographical Series no. 39.
11. Kimura Itsuro, 1993. Report of Cooperation Study on Thorium Fuel Cycle as promising Energy Source in and after the 21st Century. Kyoto University, Kyoto, Japan.
12. Lung, M., 1997. A Present Review of the Thorium Nuclear Fuel Cycles, EUR 17771, European Commission.
13. Mac Evan, J.R., 1982. R&D Program for the Thorium Fuel Cycle. AECL, Chalk River, Ont., Canada.Meriel, Y., 1967. Promesses et désavantages du thorium, deuxième Combustible Nucléaire. Sci. Prog. Nat. 3390 (October) 378-384.
14. Murogov, V.M. et al., 1994. Pu/Th/U Cycle, Fuel Cycle free from Plutonium, IPPE, Obninsk.Slessarev. I.S., Morozov, A.G., Tsourikov, D.F., 1985. Thorium Utilization in Solving the Nuclear Power Fuel Problems. Kurtchatov Institute, Moscow, IAEA, TECDOC-412.
15. Srinivasan, M., Kimura, I., 1990. Proceedings on the Indo-Japanese Seminar, Bombay, India, December, 1990.Thorn, J.D., John, C.T., Burstall, R.F., 1979. Thorium Fuel Cycles. ND-R-442(R), UKAEA.
16. Wyner, F.G. (Ed.) 1968. Second International Symposium at Gatlinburg. TN. USA, May, 1966.
17. Zhang, J.H. et al., 1985. Basic Research on Utilization of Thorium-based Nuclear Fuel. Shanghai Institute of Nuclear Research, IAEA.
18. Bastien, D., 1993. Réacteurs à haute température. In: Techniques de l'Ingénieur, B (3190) 1-19.
19. Haubenreich, P.N., 1966. Operation of the molten salt reactor experiment. In: Second International Symposium on Thorium Fuel Cycle, Gatlinburg, TN, USA.
20. IAEA, 1969. Advanced and high temperature gascooled reactors. In: Symposium at Jülich, October, 1968.
21. Kakodkar, A., Balakrishnan, K., 1990. Advanced heavy water reactor (AHWR). Indo-Japan Seminar, Bombay, India, December 1990.
22. K.F.A. Jülich, Siemens, A.G., 1979-88. Nukem GmbH, Nuclebras, Thorium Utilization in PWRs, Final Report.
23. McNeese et al., 1971-75. Molten Salt Reactor Programme. ORNL-5078, Semi-annual Reports.
24. Radkowsky, A., Galperin, A., 1997. The non-proliferative light water thorium reactor, a new Approach to LWR core technology. Nucl. News, submitted.
25. Shaw, E.H., 1975? Europe's Nuclear Power Experiment: History of the OECD Dragon project. Pergamon, Oxford.
26. Teuchert, E., 1991. Thorium utilization in high temperature reactors with advanced safety features. In: K.F.A. Jülich, (Ed.), Seminar at Kyoto University, Kyoto, Japan, October, 1991.
27. Bowman et al., 1992. Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source. In: Nuclear Instruments and Methods in Physics Research A.320.
28. Furukawa, K., Lecocq, A., Kato, Y., Mitachi, K., 1990. Thorium molten salt nuclear energy synergetics. J. Nucl. Sci. Technol. 27 (12).
29. Furukawa, K., Nakamura, N. et al., 1981. Single-fluid type accelerator molten-salt breeder concept. J. Nucl. Sci. Technol. 18 (1), 79.
30. Jongen, Y., 1994. A Proton-Driven, Intense, Subcritical, Fission Neutron Source for Radioisotope Production. IBA, Brussels, Belgium.
31. Landeyro, P.A., Guidotti, M., 1997. ENEA, Accelerator-driven systems, their applications to the incineration of long-lived radioactive waste. Rome, Italy.
32. Lewis, W.B., 1965. ACE Symposium on the Generation of Intense Neutron Fluxes. Chalk River, Ont., Canada, AECL 2177.
33. Magill, J. et al., 1995. Advantages and Limitations of Thorium-Fuelled Energy Amplifiers. EC, JRC, ITU, Karlsruhe, Germany, IAEA.
34. Rubbia, C., Carminati, F., et al., 1994. The energy amplifier. In: Presentation at CERN, Jan 1994. Presentation at the European Parliament, March 1994.
35. Rubbia, C., Rubio, J.A. et al., 1995. Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier. CERN.
36. Rubbia, C., Buono, S. et al., 1995. A Realistic Plutonium Elimination Scheme with Fast Energy Amplifier and Thorium-Plutonium Fuel.
37. CERN.Salvatores, M., Slessarev, I., Tchistiakov, A., Ritter G., 1996. The Potential of Accelerator-driven Systems for Transmutation or Power Production using Thorium or Uranium Fuel Cycles. CEA-DRN, Cadarache.
38. Sosnin, V.N., Korovin, Yu.A., 1994. Two Approaches to Neutron Production for Accelerator Breeding and Radwaste Transmutation. INPE, Obninsk, 8th Journée Saturne.
39. Steinberg, M. et al., 1976. The Clean Breeder Machine: A Preliminary Analysis and Proposal. BNL 22 114, USA.
40. Van Geel, J. et al., 1994. Accelerator-Driven Nuclear Energy Systems and The Thorium Fuel Cycle. JRC, ITU Karlsruhe, Ispra.
41. Jayaram, K.M.V., 1987. An Overview of World Thorium Resources, Incentives for Further Exploration and Forecast for Thorium Requirements in the Near-Future. DEA Hyderabad, IAEA TECDOC 412, Vienna, Austria.
42. Gmelin Handbook, 1988. Recovery of Thorium from Ores. Thorium Suppl. A2.
43. Keni, V.S., 1970. Extraction and refining of thorium, BARC. In: Proceedings of Indo-Japan Seminar on Thorium Utilization, Bombay, India, December, 1970.
44. OECD-NEA, 1965. World Uranium and Thorium Resources. Paris, France.
45. Allen, 1988. Gmelin Handbook, Thorium Supple. A3.
46. Botswell, J.M. et al., 1966. Production of U-233 with low U-232 content, E.I. du Pont de Nemours, Savannah River. In: Second International Symposium on the Thorium Fuel Cycle, Gatlinburg, TN, USA.
47. Brooksbank et al., 1966. The impact of kilorod facility operational experience on the design of fabrication plants for U-223/Th fuels, ORNL. In: Second International Symposium on the Thorium Fuel Cycle, Gatlinburg, TN, USA.
48. Kosiancic, E.J. et al., 1966. B&W, Second International Symposium on the Thorium Fuel Cycle, Gatlinburg, TN, USA.
49. Prasad, G.J., Ganguly, C., 1990. Production of Al-clad U-233 alloy fuel plates for Purnima III/ Kamini reactors. In: Proceedings of the Indo-Japan Seminar on Thorium Utilization, Bombay, India, December, 1990.
50. Sease, J.D. et al., 1966. Remote fabrication of thorium fuels, ORNL. In: Second International Symposium on the Thorium Fuel Cycle, Gatlinburg, TN, USA.
51. Sease, J.B. et al., 1964. Thorium-Uranium-233 oxide (Kilorod) facility. ORNL 3539, 102.
52. Balasubramanian, G.R., 1992. Transportation, handling and processing of irradiated thorium rods. IGCAR, Kalpakkam, India, IMech, E.
53. Candelieri, T., 1985. Operative Experience in First Campaign for Reprocessing of Uranium-Thorium Elk River Fuel Elements. ENEA, Italy, IAEA TECDOC 412.
54. K.F.A. Jülich, 1978. Fachseminar zur Wiederaufarbeitung und Entsorgung in Thorium - Brennstoffkreislauf.
55. Merz, E., 1982. Reprocessing of Th-232/U-233 fuels. In: Gmelin Handbook, Thorium Suppl. A4.
56. Nicholson, E.L. et al., 1966. Recent developments in thorium fuel processing. In: Second Symposium on Thorium Fuel Cyle, Gatlinburg, TN, USA.
57. Rathvon, H.C., Blasewitz, A.G. et al., 1966. Recovery of U-233 from irradiated thoria. In: Second Symposium on Thorium Fuel Cycle, Gatlinburg, TN, USA.
58. Short, G.D.C., Orsenigo, G., Romberg, E., 1966. Reprocessing of U-Th fuel for HGTRs - Dragon project. In: Second Symposium on Thorium Fuel Cycle, Gatlinburg, TN, USA.
59. Vietzke, H., 1988. Reprocessing of spent HTR fuel elements, Nukem. In: Gmelin Handbook, Thorium Suppl. A3.
60. Whatley, M.E. et al., 1966. Engineering development of on-site processing for molten-salt breeder reactors. In: Second Symposium on Thorium Fuel Cycle, Gatlinburg, TN, USA.
61. Dingankar, M.V., 1994. Reevaluation of Potential Hazards from Long-lived Wastes generated in the Th/U-233 Cycle in the light of ICRP-61. BARC, India.
62. IAEA, 1987. Safe Management of Wastes from the Mining and Milling of Uranium and Thorium Sources, Safety Series no. 85.
63. Jaiswal et al., 1990. Studies on biokinetics and radiation safety of thorium, BARC. In: Indo-Japan Seminar on Thorium Fuel Utilization, Bombay, India, December, 1990.
64. Naka, T., Takeda, T., 1990. Actinide production analysis for Th/U-233 LWR cycle, Osaka University. In: Indo-Japan Seminar on Thorium Utilization, Bombay, India, December, 1990.
65. Rütten, H.J., Schulten, R., Teuchert, E., 1980. Begrenzung der Toxizität von Aktiniden Waste. In: K.F.A. Jülich, Atomwirtschaft, July, 1980.