Progress and discussion on chemical separation technologies for nuclear fuel reprocessing developed abroad

Progress in Chemistry

Volumn 23, Issue 7, 2011, Pages 1272-1288

  Wei, Yuezhou ^a  

^a SHANGHAI JIAO TONG UNIVERSITY   (China)

Author keywords

Chemical separation; Dry reprocessing; Spent nuclear fuel; Wet reprocessing

Indexed keywords

EID: 80051914076     PISSN: 1005281X     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (73)

1. Benedict M, Pigford T H, Levi H W. Nuclear Chemical Engineering (2nd Edition), 1981, McGraw-Hill
2. Takahashi K. Ronbunshi of Atomic Energy Society of Japan, 2006, 5(2):152-165 (in Japanese)
3. Research Organization for Information Science & Technology. Gensiryokuhyakkajiten ATOMIC A, http://www.rist. or. jp/atomica/ (in Japanese)
4. ISIS (Institute for Science and International Security), Status and Stocks of Military Plutonium in the Acknowledged Nuclear Weapon States, (2004), http://www.isis-online.org
5. Nuclear Weapon Archive, France's Nuclear Weapons: French Nuclear Facilities. Marcoule (2001), http://nuclearweaponarchive.org
6. Suzuki A. Plutonium, The University of Tokyo Publisher, 1994 (in Japanese)
7. Yu H, Hu Y. Fuel Cycle Inside FBR, Studies on Development Strategy of Nuclear Fuel Cycle in China (Consulting Report of the Chinese Academy of Science), 2010 (in Chinese)
8. Akimoto Y. Subjects in Nuclear Policies Faced by Japan, The Lecture at Kansai Electric Power Company. 6 July, 2005 (in Japanese)
9. Wei Y Z, Arai T, Kumagai M. A Study on FBR Fuel Reprocessing by Ion Exchange Method, JNC TJ94002000-002 (in Japanese)
10. Atomic Energy Society of Japan. Overview of Partitioning and Transmutation Technology Development, Chapter 4, 2004 (in Japanese)
11. IAEA: Spent Fuel Reprocessing Options, IAEA-TECDOC-1587 (2008)
12. Research Committee on Partitioning and Transmutation Cycle of AESJ. Status and Perspectives of Partitioning and Transmutation Technology. Journal of AESJ, 2008 (3) 158-163 (in Japanese)
13. A Report of Japan Atomic Energy Commission Attached papers: http://www.aec. go. jp/jicst/NC/senmon/bunri/siryo/bunri03/siryo2-2.pdf (in Japanese)
14. Uchiyama G, Hotoku S, Fujine S, Maeda M. Nucl. Technol., 1998, 122(2):222-227
15. Todd T A, Felker L K, Vienna J D, Bresee J, Lesica S. The Advanced Fuel Cycle Initiative Separations and Waste Campaign: Accomplishments and Strategy, Proceedings of GLOBAL 2009. Paris, Sep. 8-11, 2009, 9111
16. Phillips C, Arm S, Banfield Z, Taylor R. Use of Pilot Plants for Developing used Nuclear Fuel Recycling Facilities. Proceedings of GLOBAL 2009. Paris, Sep. 8-11, 2009, 9509
17. Nash K L, Grimes T S, Nilsson M. Fundamental Studies of TALSPEAK Chemistry for Trivalent Actinide-Lanthanide Separations in Advanced Nuclear Fuel Cycles. Proceedings of GLOBAL 2009. Paris, Sep. 8-11, 2009, 9457
18. Board of Inquiry Report: Fractured Pipe with Loss of Primary Containment in the THORP Feed Clarication Cell, BNFL. May 2005, http://www. britishnucleargroup. com/
19. Nakahara M, Sano Y, Koizumi T. U, Pu and Np Co-recovery in Simplified Solvent Extraction Process, JAEA-Research 2008-078 (in Japanese)
20. Tachimori S. ARTIST Process: A Novel Chemical Process for Treatment of Spent Nuclear Fuel, JAEA-Research 2001-O48 (in Japanese)
21. Tachimori S, Suzuki S, Sasaki Y. Journal of AESJ, 2001, 43(12):1235 (in Japanese)
22. Tachimori S, Sasaki Y, Suzuki S. Solvent Extr. Ion Exch., 2002, 20(6):687-699
23. CEA Textbook: Le Traitement-Recyclage du Combustible Nucleaire Use. 2008
24. Warin D, Poinssot C, Baron P, Lorrain B. Advanced Processes for Actinide Partitioning: Recent Experiments and Results, Proceedings of GLOBAL 2009. Paris, Sep. 8-11 2009, Paper 9531
25. Miguirditchian M, Sorel C, Carries B, Bisel I, Baron P, Espinoux D, Calor J N, Viallesoubranne C, Lorrain B, Masson M. HA Demonstration in the Atalante Facility of the Ganex 1st Cycle for the Selective Extraction of Uranium from HLW, Proceedings of GLOBAL 2009. Paris, Sep. 8-11 2009, 9377
26. Wei Y Z, Kumagai M, Takashima Y, Bruggeman A, Gyseman M. J. Nucl. Sci. Technol., 1999, 36:304-306
27. Wei Y Z, Kumagai M, Takashima Y, Sawa T, Bruggeman A, Gyseman M. An Advanced Ion Exchange Process for Reprocessing Spent Nuclear Fuels-Separation of Real Spent Fuel Solutions and Conceptual Design of the Process, Proc. Global 2001, Paris, Sep. 8-11, 2001, 003
28. Wei Y Z. J. Ion Exchange, 2005, 16(2):102-114
29. Ikeda Y, Wada E, Harada M, Chikazawa T, Kikuchi T, Mineo H, Morita Y, Nogami M, Suzuki K. J. Alloys Comp., 2004, 374:420-425
30. Y. Morita, Morita Y, Kawata Y, Mineo H, Koshino N, Asanuma N, Ikeda Y, Yamasaki K, Chikazawa T, Tamaki Y, Kikuchi T. J. Nucl. Sci. Technol., 2007, 44:354-360
31. Takaki N, Shinoda Y, Watanabe M, Yoshida K. ORIENT-CYCLE-Evolutional Recycle Concept with Fast Reactor for Minimizing High-Level Waste, Proc. of The Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning & Transmutation, Oct. 14-16, 2002, Korea, 2003
32. Koyama S, Ozawa M. Advanced ORIENT Cycle Study (Phase I) (8) Summary and Prospect, Proceedings of 2010 Fall Meeting of Atomic Energy Society of Japan (in Japanese)
33. Shimada T, et al. Development on Direct Extraction of Uranium and Plutonium from Spent Fuel by Super-DIREX Reprocessing Method (19), Proceedings of 2005 Spring Meeting of Atomic Energy Society of Japan (in Japanese)
34. Suyama K, Shimada T, Ishihara N, Kuroda K, Mori Y, Ishida Y. Development of Nuclear Fuel Recycle System by Using Supercritical Fluid Carbon Dioxide for the Transition Period from LWR to FBR, Global 2009, Paris, 2009. 9385
35. Horwitza E P, Kalinaa D C, Diamonda H, Vandegrifta G F, Schulzb W W. Solvent Extr. Ion Exch., 1985, 3(1/2):75-109
36. Weaver B, Kappelmann F A. TALSPEAK; A New Method of Separating Americium and Curium from the Lanthanides by Extraction from an Aqueous Solution of an Aminopolyacetic Acid with a Monoacidic Organophosphate or Phosphonate, ORNL-3559, 1964
37. Madic C, Blanc P, et al. Actinide Partitioning from High Level Liquid Waste Using the Diamex Process", Proc. of Record'94, 1994, vol. 3 (poster session:actinide separation)
38. Baron P, Heres X, Lecomte M, Masson M. Separation of the Actinides: the DIAMEX-SANEX Concept, Proc. of Global 2001, 2001
39. Rostaing C, Baron P, Warin D, Duhamet J, Ochem D. Advanced Processes for Minor Actinides Recycling: Studies Towards Potential Industrialization, Proceedings of GLOBAL 2009, Paris, 2009. 9380
40. Pochon P, Sans D, Lartigaud C, Bisel I. Management of High Level Radioactive Aqueous Effluents in Advanced Partitioning Process, Proceedings of GLOBAL 2009, Paris, 2009. 9114
41. Morita Y, Yamaguchi I, Fujiwara T, Mizoguchi K, Kubota M. Cold and Semi - Hot Tests of 4 - Group Partitioning Process at NUCE F, JAERI-Research, 2000, 2000-24 (in Japanese)
42. Kubota M, Morita Y. Preliminary Assessment on Four Group Partitioning Process Developed in JAERI, Proc. of Global'97, 1997. vol. 1:458
43. Ozawa M, Koma Y, Nomura K, Tanaka Y. J. Alloy. Compounds, 1998, 271/273:538-543
44. Koma Y, Watanabe M, Nemoto S, Tanaka Y. Solvent Extr. Ion Exch., 1998, 16(6):1357-1367
45. Japan Atomic Energy Agency, The Japan Atomic Power Company. Feasibility Study on Commercialized Fast Reactor Cycle System (Phase II), Final Report, March 2006 (in Japanese)
46. Japan Science and Technology Agency, Innovative Nuclear Research and Development program - Special Promotion Area, July 2006. http://www.jst. go. jp/nrd/bosyu/hl8tokushinbosyu.html (in Japanese)
47. http;//www.aec. go. jp/jicst/NC/senmon/bunri/siryo/bunri03/siryo2-2.pdf
48. Wei Y Z, Hoshi H, Kumagai M, Asakura T, Morita Y. J. Alloys Compounds, 2004, 374(1/2):447-50
49. Hoshi H, Wei Y Z, Kumagai M, Asakura T, Morita Y. J. Alloys Compounds, 2004, 374(1/2):451-455
50. Wei Y Z, Hoshi H, Kumagai M, Asakura T, Uchiyama G. J. Nucl. Sci. Technol., 2002, Suppl. 3:761
51. Wei Y Z, Hoshi H, Morita Y, Bruggeman A, Goethals P. Separation of Am and Cm from HLLW by Extraction Chromatography Using Novel R-BTP Extraction Resins, Proceedings of Global'2009, Paris, 2009. 9390
52. Adnet J M, Donnet L, Chartier D, Bros P, Fire N, Brossard P. The Development of the SESAME Process, Proc. of Global'97, 1997. vol. 1:592
53. Suzuki T, Takahashi K, Nogami M, Nomura M, Ozawa M, Koyama S, Mimura H, Fujita R, Fujii Y. Concept of Advanced Spent Fuel Reprocessing based on Ion Exchange, GLOBAL 2007, USA. 2007
54. Kubota M. Radiochimica Acta, 1993, 63:91-96
55. Kubota M, Yamaguchi I, Morita Y, Yamagishi I. Radiochemistry, 1997, 39:299-303
56. 99Tc from Real Effluents by Crown Ethers, Proc. of Global'99, 1999
57. Dozol J F, Lamare V, Simon N, Eymard S, Rouquette H, Tournois B. New Calix[4] Crown for the Selective Extraction of Cesium, Proc. of Global'97, 1997, vol. 2:1517
58. Horwitz E P, Dietz M L, Fisher D E. Solvent Extr. Ion Exch., 1991, 9 (1); 1-25
59. Wood D J, Law J D, Herbst R S, Todd T A. Removal of Sr and Hg from Acidic Liquid Radioactive Waste by Solvent Extraction with the SREX Process, Proc. of Global'99, 1999
60. Inoue M, et al. Development of Pyropartitioning of Transuranium Elements from High-Level Liquid Waste, CRIEPI Research Report, 1998. T57 (in Japanese)
61. Kurata M, Kinoshita K, Hijikata T, Inoue T. J. Nucl. Sci. Technol., 2000, 37(8):682-690
62. Uozumi K, Kinoshita K, Inoue T, Fusselman S P, Grimmett D L, Roy J J, Storvick T S, Krueger C L, Nabelek C R. J. Nucl. Sci. Technol., 2001, 38(1):36-44
63. Kinoshita K, Kurata M, Inoue T. J. Nucl. Sci. Techmol., 2000, 37(1):75-83
64. Iizuka M, Uozumi K, Inoue T, Iwai T, Shirai O, Arai Y. J. Nucl. Mater., 2001, 299:32-42
65. Ahn D H. Development of the Electrowinning System for TRU Recovery in Korea, The 9 Joint Workshop between China and Korea on Nuclear Waste Management and Nuclear Fuel Cycle, 2010, China
66. Harman K M, Jansen G Jr. The Salt Cycle Process, Progress in Nuclear Energy Series III, Process Chemistry, 1970, vol. 4:429
67. Bychkov A V, Vavilov S K, Porodnov P T, Skiba O V. Pyroelectrochemical Reprocessing of Irradiated Uraniumplutonium Oxide Fuel for Fast Reactors, Proc. of Global'93, 1993, vol. 2:1351
68. Ivanov V B, Mayorshin A A, Skiba O V. et al. The Utilization of Plutonium in Nuclear Reactors on the Bases of Technologies, Developed in SSC RIAR, Proc. of Global'97, 1997, vol 2:1093
69. Suzuki K, Namba T, Asou M, et al. Feasibility Study of Pyrochemieal Recovery of Actinide from MOX Fuel, Proc. of Global' 95, 1995, vol 2:1200
70. Asou M, Hasuike T, Tamura S, et al. A Modular Recycling Plant Concept, Flexible to Future Fuel Cycle Demands, Proc. of Global'97, 1997, vol. 2:894
71. Aso M, Mizuguchi K, Shoji Y, Kobayashi T. Theoretical Evaluation of Decontamination Methods for Noble Metals in Oxide Electrowinning Process, Proc. of Global 2001, 2001
72. Kani Y, Sasahira A, Hoshino K, Kawamura F. Journal of Fluorine Chemistry, 2009, 130(1):74-82
73. Akai Y, Fujita R. J. Nucl. Sci. Technol., 1995, 33:1064-1066