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The world's demand for energy will increase because the quality of living is tied to its consumption and because the world's population is increasing. It is well known that high quality energy sources such as electricity and oil are directly linked to economic growth and quality of life (e.g., access to food, medicine, housing and education). As more countries participate in the benefits of globalization, world energy use will grow. For example, in the past decade prior to the financial collapse of world markets that occurred during October of 2008, two of the world's most populated countries, China and India, had unprecedented economic growth and this played a major role in the price of oil climbing to nearly $150 per barrel during the summer of 2008. The year 2008 also saw an precipitous drop in oil prices as well. It is well known that economic growth is cyclic and that during periods of recession, demand for energy decreases. After October of 2008 the price of oil dropped under $45 dollar per barrel. As of this writing the world was still in the recession of 2008, but history tells us that a recovery will occur and that during the next economic growth period oil prices will once again rise. The other factor which impacts growth in energy demand is growth in population. The US Census Bureau has projected that the world population will increase to 9 billion people by 2042 from approximately 6.6 billion people today. The future holds more uncertainty. The competition for scarce energy resources will only accelerate as more people in the world participate in the economic benefits of globalization and as world population grows.

One of the requirements for sustaining human life and progress is availability of a clean source of energy that does not harm the environment. The release of CO2 into the atmosphere is the main cause of global warming and various associated climate changes. A major advantage of nuclear energy is that it doesn't put CO2 into the atmosphere. In addition it provides a steady source of constant electrical power that does not suffer the whim of weather patterns. This is a critical feature because climate change does impact weather patterns. For example, areas which currently have an abundance of wind or clear skies for solar energy use today may experience a change over the 30 or so year lifetime of a wind farm or a solar energy plant.

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References

  1. US Department of Energy (1993) DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory: Volume 1 and 2. DOE-HDBK 1019/1–93

    Google Scholar 

  2. National Nuclear Data Center. Chart of nuclides. Brookhaven National Laboratory. http://www.nndc.bnl.gov/chart/

  3. Heeger K (2008) Fission and nuclear energy Lecture 21 University of Wisconsin.

    Google Scholar 

  4. Prelas MA, Peck MS (2005) Nonproliferation Issues for Weapons of Mass Destruction. CRC Press, New York, USA

    Google Scholar 

  5. World Nuclear Association, London, UK

    Google Scholar 

  6. NEA/IAEA (OECD Nuclear Energy Agency and International Atomic Energy Agency), 2006: Uranium 2005: Resources, Production and Demand. A joint report by the OECD Nuclear Energy Agency and the International Atomic Energy Agency Publication No. 6098. OECD, Paris (2006).

    Google Scholar 

  7. Rogner H-H, McDonald A (November 2007) Nuclear Energy — Status and Outlook, 20th World Energy Congress, Rome, Italy

    Google Scholar 

  8. U.S. Nuclear Regulatory Commission, 2008.

    Google Scholar 

  9. Cochran R, Tsoulfanidis N (1999) The Nuclear Fuel Cycle: Analysis and Management, 2nd Edition. American Nuclear Society, La Grange Park, Illinois.

    Google Scholar 

  10. Argonne National Laboratory. Depleted UF6 management information network. http://web.ead.anl.gov/uranium/index.cfm. 12/18/2008.

  11. U.S. Nuclear Regulatory Commission. Fact sheet on uranium enrichment. http:// www.nrc.gov/reading-rm/doc-collections/fact-sheets/enrichment.html. 12/18/2008.

  12. Wood HG, Glaser A, Kemp RS (2008) The gas centrifuge and nuclear weapons proliferation. Physics Today September: 40–15

    Google Scholar 

  13. USEC. http://www.usec.com/v2001_02/HTML/Aboutusec_enrichment.asp.

  14. Heller A (May 2000) Laser Technology Follows in Lawrence's Footsteps. Science and Technology Review. https://www.llnl.gov/str/str2000.html.

  15. Hargrove S (May 2000) Laser Technology Follows in Lawrence's Footsteps. Science and Technology Review. www.llnl.gov/str/Hargrove.html.

  16. Wilson PD (1996) The Nuclear Fuel Cycle. Oxford University Press, New York.

    Google Scholar 

  17. Fouquet DM, Razvi J, Whittemore WL (November 2003) TRIGA research reactors: A pathway to the peaceful applications of nuclear energy. Nuclear News: 46–56.

    Google Scholar 

  18. US DOE, National Transportation Program. Spent nuclear fuel and high-level radioactive waste transportation. http://www.nti.org/e_research/official_docs/doe/ spent_nuc_feul.pdf.

  19. Wallace WP, Simnad MT (1964) Fuel element. U.S. Patent No. 3,119,747, January 28, 1964.

    Google Scholar 

  20. European Nuclear Society. Fuel rod. www.euronuclear.org/info/encyclopedia/f/ fuel-rod.htm. 12/18/2008

  21. Keiser DD, Jr., Kennedy JR, Hilton BA, and Hayes SL (2008) The development of metallic nuclear fuels for transmutation applications: Materials challenges. JOM Journal of the Minerals, Metals and Materials Society 60(1): 29–32

    Google Scholar 

  22. OECD (Organisation for Economic Co-operation and Development) (2006) Red Book Retrospective. A review of uranium resources, production and demand from 1965 to 2003.

    Google Scholar 

  23. Arbital JG, Snider JD (1996) Technology for down-blending weapons grade uranium into commercial reactor-usable uranium. Nuclear Materials Management — Annual Meeting 25: 890–895

    Google Scholar 

  24. U.S. Department of Energy (2002) A technology roadmap for Generation IV nuclear energy systems. U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002, GIF-002-00. http:// www.ne.doe.gov/GenIV/documents/gen_iv_roadmap.pdf

  25. Stacey WM (2001) Nuclear Reactor Physics. Wiley-Interscience, New York

    Google Scholar 

  26. J. Kenneth Shultis and Richard E. Faw (2007) Fundamentals of Nuclear Science and Engineering, 2nd Ed. CRC Press, New York, USA

    Google Scholar 

  27. Lamarsh JR, Baratta AJ (2001) Introduction to Nuclear Engineering 3rd Ed. Addison-Wesley Series in Nuclear Science and Engineering. Prentice Hall, Upper Saddle River, NJ

    Google Scholar 

  28. Hore-Lacy I (2006) Nuclear Energy in the 21st Century. World Nuclear University Press/Academic Press, London, UK

    Google Scholar 

  29. Bodansky, D (1996) Nuclear Energy: Principles, Practices, and Prospects. American Institute of Physics. Woodbury, NY

    Google Scholar 

  30. Knief RA (1992) Nuclear Engineering: Theory and Technology of Commercial Nuclear Power, Taylor and Francis

    Google Scholar 

  31. Glasstone S, Sesonske A (1994) Nuclear Reactor Engineering, 4th Ed. Chapman and Hall, New York

    Google Scholar 

  32. USNRC Technical Training Center. Boiling water reactor systems, Reactor Concepts Manual, Nuclear Regulatory Commission). http://www.nrc.gov/reading-rm/basic-ref/ teachers/01.pdf

  33. USNRC Technical Training Center. Nuclear power for electrical generation, Reactor Concepts Manual, Nuclear Regulatory Commission). http://www.nrc.gov/reading-rm/ basic-ref/teachers/03.pdf

  34. USNRC Technical Training Center. Pressurized water reactor system, Reactor Concepts Manual, Nuclear Regulatory Commission). http://www.nrc.gov/reading-rm/ basic-ref/teachers/04.pdf

  35. Murray RL (2007) Nuclear Reactors. Kirk-Othmer Encyclopedia of Chemical technology. Wiley, Malden, MA.

    Google Scholar 

  36. Nuclear Energy Institute, Washington D.C., USA

    Google Scholar 

  37. General Electric (3/30/2009) BWR/6 fuel assemblies and Control rod module. www. nucleartourist.com/images/bwrfuel1.jpg

  38. The Institute of Engineering and Technology. Nuclear Reactor Type. www.theiet.org/ factfiles.

  39. Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies. IAEA-TECDOC-1197, 2001. http:// www.pub.iaea.org/MTCD/publications/PDF/te_1197_prn.pdf)

  40. IAEA (International Atomic Energy Agency) (2005) Accident analysis for nuclear power plants with graphite moderated boiling water RBMK reactors. Safety Report Series No. 43.

    Google Scholar 

  41. Advanced Boiling Water Reactor Fact Sheet. http://www.gepower.com/prod_serv/ products/nuclear_energy/en/downloads/abwr_fs.pdf.

  42. AP1000 at a Glance. http://ap1000.westinghousenuclear.com/ap1000_glance.html

  43. Long LB, Cummins WE, Winters JW. (2006) AP1000 Design for Security 2006 International congress on advances in nuclear power plants — ICAPP′06, Reno-Nevada USA, June 4–8 2006

    Google Scholar 

  44. Kasper K (2006) New Nuclear Options-The AP1000. Health Physics 90(6): 519–520

    Google Scholar 

  45. AP1000 Design Control Document (2004) Revision 14, September 2004 (Revision 0 sent to NRC March 2002).

    Google Scholar 

  46. Matzie RA (2008) AP1000 will meet the challenges of near-term deployment. Nuclear Engineering and Design 238(8): 1856–1862

    Google Scholar 

  47. Schulz TL (2006) Westinghouse AP1000 advanced passive plant. Nuclear Engineering and Design 236: 1547–1557

    Google Scholar 

  48. Mitsubishi Heavy Industries, Ltd., DOE Technical Session, UAP-HF-07063-12, June 29, 2007).

    Google Scholar 

  49. US EPR, Areva. http://www.areva-np.com/us/liblocal/docs/EPR/U.S.EPRbrochure_ 1.07_FINAL.pdf).

  50. Gamble RE, Hinds DH, Hucik SA, Maslak CE (2006) ESBWR… An Evolutionary Reactor Design Conference: 2006 International congress on advances in nuclear power plants — ICAPP'06, Reno — Nevada, USA, June 4–8, 2006. Proceedings of the 2006 international congress on advances in nuclear power plants – ICAPP '06

    Google Scholar 

  51. Cheng YK, Shiralkar BS, Marquino W (2005) Performance analyses of ESBWR ECCS and containment systems. Proceedings of ICAPP ′05 Seoul Korea Paper 5485

    Google Scholar 

  52. Hinds D, Maslak C (January 2006) Next-generation nuclear energy: ESBWR. Nuclear News: 35–40

    Google Scholar 

  53. ESBWR, Technical fact sheet (http://www.energetics.com/pdfs/nuclear/esbwr.pdf)

  54. Carelli MD, Conway LE, Oriani L, Petrović B, Lombardi CV, Ricotti ME,Barroso ACO, Collado JM, Cinotti L, Todreas NE, Grgić D, Moraes MM, Boroughs RD, Ninokata H, Ingersoll DT, Oriolo F (2004) The design and safety features of the IRIS reactor. Nuclear Engineering and Design 230(1–3): 151–167

    Google Scholar 

  55. Carelli MD, Petrovic B, Ferroni P (2007) IRIS safety-by-design and its implication to lessen emergency planning requirements. International Journal of Risk Assessment and Management 8(1–2): 123–136

    Google Scholar 

  56. Carelli MD, Conway L, Oriani L, Lombardi C, Ricotti M, Barroso A, Collado J, Cinotti L, M. Moraes M, Kozuch J, Grgic D, Ninokata H, Boroughs R, Ingersoll D, Oriolo F, Carelli MD (2003) The design and safety features of the Iris reactor. 11th International Conference on Nuclear Engineering Tokyo, Japan, April 20–23, 2003 ICONE11- 36564

    Google Scholar 

  57. Paramonov DV, Carelli MD, Miller K, Lombardi CV, Ricotti ME. Todreas NE, E. Greenspan E, Yamamoto K, Nagano A, Ninokata H, J. Robertson J, Oriolo F. IRIS reactor development. http://www2.ing.unipi.it/dimnp/CD/supporto/pdf/oriolo03.pdf.

    Google Scholar 

  58. Natsionalna Elektricheska Kompania Joint Press Release (2008). http://www.nek.bg/ cgi-bin/index.cgi?l=2&d=1254

    Google Scholar 

  59. Hedges K (2002) The advanced CANDU reactor (ACR): Ready for the emerging market. ANES 2002 Symposium, October 16–18, 2002, Miami, FL

    Google Scholar 

  60. Lennox TA, Banks DM, Gilroy JE, Sunderland RE (1998) Gas cooled fast reactors. Trans. ENC 98 IV, TAL/005392

    Google Scholar 

  61. Melese-d'Hospital G, Simon RH (1977) Status of gas-cooled fast breeder reactor programs. Nuclear Engineering and Design 40: 5–12

    Google Scholar 

  62. Dostal V, Hejzlar P, Driscoll MJ, Todreas NE (2002) A supercritical CO2 gas turbine power cycle for next generation nuclear reactors. 10th International Nuclear Conference on Engineering (ICONE 10), Arlington, Virginia, USA, April 14–18, 2002

    Google Scholar 

  63. Martin P, Chauvin N, Garnier JC, Masson M, Brossard P, Gas cooled fast reactor system: Major objectives and options for reactor, fuel and fuel cycle. Proceedings of GLOBAL 2005 Tsukuba, Japan, October 9–13, 2005 Paper No. IL002

    Google Scholar 

  64. Anzieu P, Mizuno T, Okano Y, Aida T (2005) Conceptual core design studies of helium cooled fast reactor with coated particle fuel, Paper 5197, 2005 International Congress on Advances in Nuclear Power Plants (ICAPP′05)

    Google Scholar 

  65. Wei TYC, Rouault J (2003) Development of Generation IV advanced gas-cooled reactors with hardened/fast neutron spectrum. Transactions of the American Nuclear Society 88: 683–684

    Google Scholar 

  66. Cheng LY, Ludewig H (2007) 2400MWt gas-cooled fast reactor DHR studies status update. Brookhaven National Laboratory Report No. BNL–78166-2007

    Google Scholar 

  67. Meyer MK, Fielding R, Gan J (2007) Fuel development for gas-cooled fast reactors. Journal of Nuclear Materials 371(1–3): 281–287

    Google Scholar 

  68. Cinotti L, Smith CF, Sienicki JJ, Aït Abderrahim H, Benamati G, Locatelli G, Monti S. Wider H, Struwe D, Orden A (2007) The potential of the LFR and the ELSY project. 2007 International Congress on Advances in Nuclear Power Plants (ICAPP′07). Book of Abstracts, ICAPP 2007 Nice, France, May 13–18. Paper 7585

    Google Scholar 

  69. Yu YH, Son HM, Lee IS, Suh KY, (2006) Optimized battery-type reactor primary system design utilizing lead, Paper 6148, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP′06)

    Google Scholar 

  70. Hwang IS, (2006) A sustainable regional waste transmutation system: PEACER, Plenary Invited Paper, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP′06)

    Google Scholar 

  71. Kim WJ, Kim TW, Sohn MS, Suh KY (2006) Supercritical carbon dioxide Brayton power conversion cycle design for optimized battery-type integral reactor system, Paper 6142, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP′06)

    Google Scholar 

  72. Zrodnikov AV, Toshinsky GI, Komlev OG, Dragunov YG, Stepanov VS, Klimov NN, Kpytov II, Krushelnitsky VN, Use of multi-purpose modular fast reactors SVBR-75/100 in market conditions, Paper 6023, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP′06)

    Google Scholar 

  73. Cinotti L, Fazio C, Knebel J, Monti S, Abderrahim HA, Smith C, Suh K (2006) Lead-cooled fast reactor, FISA 2006, Luxembourg, 13–16 March 2006. UCRL-CONF-221396

    Google Scholar 

  74. Sienicki JJ, Moisseytsev AV (2005) SSTAR lead-cooled, small modular fast reactor for deployment at remote sites — system thermal hydraulic development, Paper 5426, 2005 International Congress on Advances in Nuclear Power Plants (ICAPP′05)

    Google Scholar 

  75. Azzati A, Benamati G, Gessi A, Long B, Scadozzo G (2004) Corrosion behaviour of steels in flowing LBE at low and high oxygen concentration. Journal of Nuclear Materials 335: 169–173

    Google Scholar 

  76. Nishi Y, Kinoshita I (2003) Experimental study on gas lift pump performance in lead-bismuth eutectic, ICAPP03-3055, 2003 International Congress on Advances in Nuclear Power Plants (ICAPP′03)

    Google Scholar 

  77. Toshinsky GI, Grigoriev OG, Efimov EI, Leonchuk MP (2002) Safety aspects of the SVBR-75/100 reactor, NEA Workshop on Advanced Nuclear Safety Issues and Research Needs, February 18–20, 2002, Paris, France

    Google Scholar 

  78. Adamov EO, Orlov VV, Filin A (2001) Final report on the ISTC Project 1418: Naturally safe lead-cooled fast reactor for large scale nuclear power, Moscow

    Google Scholar 

  79. Smith CF, Halsey WG, Brown NW, Sienicki JJ, Moisseytsev A, Wade DC (2008) SSTAR: The US lead-cooled fast reactor (LFR). Journal of Nuclear Materials 376(3): 255–259

    Google Scholar 

  80. Lamont A, Brown N (2005) An economic analysis of GEN-IV lead cooled fast reactor. American Nuclear Society Transactions: 49–50

    Google Scholar 

  81. Allen TR, Crawford DC (2007) Lead-cooled fast reactor systems and the fuels and materials challenges. Science and Technology of Nuclear Installations 2007: 1–9

    Google Scholar 

  82. Wider HU, Carlsson J, Loewen E (2005) Renewed interest in lead cooled fast reactors. Progress in Nuclear Energy 47(1–4): 44–52

    Google Scholar 

  83. Mitachi K, Yamamoto T, Yoshioka R (2007) Three-region core design for 200-MW(electric) molten-salt reactor with thorium-uranium fuel. Nuclear Technology 158(3): 348–357

    Google Scholar 

  84. Hron MJ, Juricek V, Kyncl J, Mikisek M, Rypar V (2007), MSR – SPHINX concept program EROS (Experimental zero power salt reactor SR-0). The proposed experimental program as a basis for validation of reactor physics methods. 2007 International Congress on Advances in Nuclear Power Plants (ICAPP′07). Paper 7424

    Google Scholar 

  85. Lecarpentier D (2006) Contribution aux travaux sur la transmutation des déchets nucléaires, voie des réacteurs a sel fondu : le concept amster, aspect physique et sûreté (Contribution to the work on radioactive waste transmutation, molten salt reactors : The Amster concept, physical aspects and safety), Doctoral dissertation, Conservatoire national des arts et métiers, Paris

    Google Scholar 

  86. Mathieu L, Heuer D, Brissot R, Le Brun C, Liatard E, Loiseaux JM, Méplan O, Merle-Lucotte E, Nuttin A, Wilson J, Garzenne C, Lecarpentier D, Walle E (2006) The thorium molten salt reactor: moving on from the MSBR. Progress in Nuclear Energy 48(7): 664–679

    Google Scholar 

  87. Forsberg C, Peterson P (2004) An advanced molten salt reactor using high-temperature reactor technology. 2004 International Congress on Advances in Nuclear Power Plants (ICAPP′04)

    Google Scholar 

  88. Forsberg C (2004) Molten Salt Reactor Technology Gaps, 2004 International Congress on Advances in Nuclear Power Plants (ICAPP′04)

    Google Scholar 

  89. Ignatiev V, Feynberg O, Mjasnikov A, Zakirov R (2003) Reactor physics and fuel cycle analysis of a molten salt advanced reactor transmuter. 2003 International Congress on Advances in Nuclear Power Plants (ICAPP′03)

    Google Scholar 

  90. MacPherson HG (1985) The molten salt reactor adventure. Nuclear Science and Engineering 90: 374–380

    Google Scholar 

  91. Mitachi K, Yamamoto T, Yoshioka R (2005) Performance of a 200 MWe molten-salt reactor operated in thorium-uranium fuel-cycle. Proceedings of GLOBAL 2005 Tsukuba, Japan, Oct 9–13, 2005 Paper No. 089

    Google Scholar 

  92. Forsberg CW, Peterson PF, Pickard PS (2002) Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity. Nuclear Technology 144(3): 289–302

    Google Scholar 

  93. Kazuo F, Hiroo N, Yoshio K, Koushi M, Ritsuo Y, Akira F, Yuzuru S, Kazuto A (2005) New primary energy source by thorium molten-salt reactor technology. Electrochemistry 73(8): 552–563

    Google Scholar 

  94. Merle-Lucotte E, Heuer D, Allibert M, Ghetta V, Brun CL, Mathieu L, Brissot R, Liatard E (2007) Optimized transition from the reactors of second and third generations to the thorium molten salt reactor. ICAPP 2007. International Congress on Advances in Nuclear Power Plants, Nice : France" May 13–18, 2007 Paper 7186

    Google Scholar 

  95. DeWitte J, Goede T, Perfetti C, Plower T, Wayson M (2007) Design analysis of an advanced molten salt burner reactor. American Nuclear Society Transactions.

    Google Scholar 

  96. Chikazawa Y, Okano Y, Konomura M, Sawa N, Shimakawa Y, Tanaka T (2007) A compact loop-type fast reactor without refueling for a remote area power source. Nuclear Technology 157(2): 120–131

    Google Scholar 

  97. Hahn D, Kim Y, Kim S, Lee J, Lee Y, Jeong H (2007) Conceptual design features of the KALIMER-600 sodium cooled fast reactor. Global 2007, Boise, USA, September 9–13, 2007

    Google Scholar 

  98. Niwa H, Aoto K, Morishita M (2007) Current status and perspective of advanced loop type fast reactor in fast reactor cycle technology development project. Global 2007, Boise, USA, September 9–13, 2007

    Google Scholar 

  99. Sienicki J, Moisseytsev A, Cho D, Momozaki Y, Kilsdonk D, Haglund R, Reed C, Farmer M (2007) Supercritical carbon dioxide brayton cycle energy conversion for sodium-cooled fast reactors/advanced burner reactors. Global 2007, Boise, USA, September 9–13, 2007

    Google Scholar 

  100. Zaetta A, Dufour Ph, Pruhliere G, Rimpault G, Thevenot C, Tommasi J, Varaine F (2007) Innovating core design for sodium cooled fast reactors of fourth generation. Paper 7383, ICAPP 2007, Nice, France, May 13–18, 2007

    Google Scholar 

  101. Chang Y, Konomura M, Lo Pinto P (2005) A case for small modular fast reactor. Global 2005, Tsukuba, Japan, October 9–13, 2005

    Google Scholar 

  102. Hahn D, Kim Y, Kin S, Lee J, Lee Y (2005) Design concept of KALIMER-600. Global 2005, Tsukuba, Japan, October 9–13, 2005

    Google Scholar 

  103. Kotake S, Sakamoto Y, Ando M, Tanaka T (2005) Feasibility study on commercialized fast reactor cycle systems/current status of the SFR system design. Global 2005, Tsukuba, Japan, October 9–13, 2005

    Google Scholar 

  104. Mizuno T, Ogawa T, Naganuma M, Aida T (2005) Advanced oxide fuel core design study for SFR in the feasibility study in Japan. Global 2005, Tsukuba, Japan, October 9–13, 2005

    Google Scholar 

  105. Lefevre JC, Mitchell CH, Hubert G (1996) European fast reactor design. Nuclear Engineering Design 162(2–3): 133–143

    Google Scholar 

  106. Chang YI (1992) A next-generation concept: The integral fast reactor (IFR), USDOE Report, Argonne National Laboratory Report No. ANL/CP-75894, CONF-9204157-1

    Google Scholar 

  107. Hishida M, Kubo S, Konomura M, Toda M (2007) Progress on the plant design concept of sodium-cooled fast reactor. Journal of Nuclear Science and Technology 44(3): 303–308

    Google Scholar 

  108. Crawford DC, Porter DL, Hayes SL (2007) Fuels for sodium-cooled fast reactors: US perspective. Journal of Nuclear Materials 371(1–3): 202–231

    Google Scholar 

  109. Yoo J, Ishiwatari Y, Oka Y, Yang J, Liu J (2007) Subchannel analysis of supercritical light water-cooled fast reactor assembly. Nuclear Engineering and Design 237: 1096– 1105

    Google Scholar 

  110. Mori M, Maschek W, Rineiski A (2006) Heterogeneous cores for improved safety performance: A case study: The supercritical water fast reactor. Nuclear Engineering and Design 236(14–16): 1573–1579

    Google Scholar 

  111. Yoo J, Ishiwatari Y, Oka Y, Liu J (2006) Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling. Annals of Nuclear Energy 33: 945–956

    Google Scholar 

  112. Yoo J, Ishiwatari Y, Liu J (2005) Composite core design of high power density supercritical water cooled fast reactor. Global 2005, Tsukuba, Japan, October 9–13, 2005, Paper No. 246

    Google Scholar 

  113. Mori M (2005) Core design analysis of the supercritical water fast reactor. For-schungszentrum Karlsruhe in der Helmholtz-Gemeinschaft, Wissenschaftliche Berichte FZKA 7160

    Google Scholar 

  114. Mori M, Maschek W, Laurien E, Morita K (2003) Monte-Carlo/Simmer-III reactivity coefficients calculations for the supercritical water fast reactor. Global 2003, New Orleans, Louisiana, November 16–21, 2003, Paper No. 87753

    Google Scholar 

  115. Mukohara T, Koshizuka S, Oka Y (1999) Core design of a high-temperature fast reactor cooled by supercritical light water. Annals of Nuclear Energy 26: 1423–1436

    Google Scholar 

  116. Oka Y, Kozhizuka S (1998) Conceptual design study of advanced power reactors. Progress in Nuclear Energy 32: 163–177

    Google Scholar 

  117. Lee JH, Oka Y, Koshizuka S (1999) Safety system consideration of supercritical water cooled fast reactor with simplified PSA. Reliability Engineering and System Safety 64: 327–338

    Google Scholar 

  118. MacDonald PE (2002) Feasibility study of supercritical light water cooled reactors for electric power production. Nuclear Energy Research Initiative Project 2001-001, Westinghouse Electric Co. Grant Number: DE-FG07-02SF22533, Final Report INEEL/EXT-04-02530

    Google Scholar 

  119. Granovskii M, Dincer I, Rosen MA, Pioro I (2008) Thermodynamic analysis of the use a chemical heat pump to link a supercritical water-cooled nuclear reactor and a thermochemical water-splitting cycle for hydrogen production. Journal of Power and Energy Systems 2(2): 756–767

    Google Scholar 

  120. Oh, C (2007) Power cycle and stress analyses for high temperature gas-cooled reactor. International Congress on Advances in Nuclear Power Plants (ICAPP 2007)

    Google Scholar 

  121. Sterbentz JW (2007) Low-enriched very high temperature reactor core design, 2007 International Congress on Advances in Nuclear Power Plants (ICAPP 2007)

    Google Scholar 

  122. Vilim RB (2007) Interface design studies for the production of hydrogen using the VHTR coupled to the HTSE process, 2007 International Congress on Advances in Nuclear Power Plants (ICAPP 2007)

    Google Scholar 

  123. Billot P, Hittner D, Vasseur P (2006) Outlines of the French R&D Program for the development of High and Very High Temperature Reactor. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  124. Fütterer MA, Toscano E, Bakker K, Berg G, Marmier A (2006) Irradiation results of AVR fuel pebbles at increased temperature and burn-up in the HFR petten. Proceedings HTR 2006, Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  125. Greyvenstein R, Correia M, Kriel W (2006) South Africa's opportunity to maximize the role of nuclear power in a global hydrogen economy. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  126. Hittner D, Bogusch E, Besson D (2006) RAPHAEL A European Project for the development of HTR/VHTR technology for industrial process heat supply and cogeneration. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  127. Hu S, Liang X, Wei L, (2006) Commissioning and operation experience and safety experiment at HTR-10. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  128. Lee Y-W, Park J-Y, Kim YK, Jeong BG, Kim YM (2006) Development of HTGR coated particle fuel technology in Korea. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  129. Takamatsu K, Nakagawa S, Takeda T (2006) Development of core dynamics analysis of coolant flow reduction tests of HTTR. Third International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa

    Google Scholar 

  130. Tsvetkov PV (2006) Coupled hybrid Monte Carlo — deterministic analysis of VHTR configurations with advanced actinide fuels. Paper ICAPP-6400, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP′06)

    Google Scholar 

  131. Kim TK, Taiwo TA, Hill RN, Stillman A (2005) Spent nuclear fuel characterization for the VHTR. Global 2005, Tsukuba, Japan, October 9–13, 2005, Paper 67

    Google Scholar 

  132. Jones AR (1975) Very high temperature reactor (VHTR) technology. 10th Rec Inter-soc Energy Convers Eng Conf: 329–337

    Google Scholar 

  133. Taketoshi A, Sadao S, Yutaro T (1977) Studies on design principles and criteria of fuels and graphites for experimental multipurpose very high temperature reactor. Report JAERI-M-7415

    Google Scholar 

  134. Katsuichi I (1982) Development of fuel for VHTR (Very High Temperature Reactor). Genshiryoku Kogyo 28(8): 53–57

    Google Scholar 

  135. Shigeru Y, Shuichi M, Osamu S, Yoshihiro T, Yasuyuki N, Takao N, Kazuo Y, Seii-chi U (1987) The study on the role of veryhightemperature reactor and nuclear process heat utilization in future energy systems. Implication in energy, economy, and environment of Japan. Nippon Genshiryoku Kenkyusho JAERI-M, JAERI-M-87-187

    Google Scholar 

  136. Christine M (2008) Using genetic algorithms to optimize the helium loop of a very high temperature reactor. Nuclear Technology 162(3): 323–332

    Google Scholar 

  137. Shohei U, Jun A, Atsushi Y, Hideharu I, Tomoo T, Kazuhiro S (2008) Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor. Journal of Nuclear Materials 376(2): 146–151.

    Google Scholar 

  138. Areva http://www.arevaresources.ca/nuclear_energy/datagb/actualites/gtmhr.htm

  139. Venneri F (2005) Destruction of nuclear waste and recycle of resources using MHR technology. IAEA, Trieste 2005

    Google Scholar 

  140. http://coal2nuclear.com/2%20TRISO_nuclear_fuel.htm#Chapter_Two,_Part_Two

  141. Takamatsu K, Nakagawa S, Takeda T (2006) Development of core dynamics analysis of coolant flow reduction tests of HTTR. Proceedings HTR2006: 3rd International Topical Meeting on High Temperature Reactor Technology, October 1–4, 2006, Johannesburg, South Africa, Paper No. C00000174.

    Google Scholar 

  142. Baldwin DE, Campbell M, Ellis C, Richards M, Shenoy A (2007) MHR design, technology and applications. ICENES 2007 Conference, Istanbul, June 03–08

    Google Scholar 

  143. Kumar A, Vittal Rao TV, Mukherjee SK, Vaidya VN (2006) Recycling of chemicals from alkaline waste generated during preparation of UO3 microspheres by sol gel process. Journal of Nuclear Material 350(1): 254–263.

    Google Scholar 

  144. Brooks LH (1969) HTGR [high temperature gas reactor] fuel reprocessing: head-end treatment of experimental small scale HTGR fuel elements. In. Gulf Gen. At., Inc., San Diego, CA, USA: 32

    Google Scholar 

  145. Byster SE (1980) Dissolution of HTGR TRISO beads by the alkali fluoride fusion method. In. New Brunswick Lab, US DOE, Argonne, IL,USA: 9

    Google Scholar 

  146. Chernikov A, Kosukhin V (2008) Deposition of ZrC coats on UO2 particles using the chloride process. Nuclear Engineering and Design 238: 2861–2865

    Google Scholar 

  147. Chernikov AS, Lyutikov RA, Kurbakov SD, Repnikov VM, Khromonozhkin VV, Solov'ev GI (1991) Behavior of HTGR coated fuel particles in high-temperature tests. Energy (Oxford, United Kingdom) 16: 295–308

    Google Scholar 

  148. Contescu CI, Baker FS, Hunt RD, Collins JL, Burchell TD (2008) Selection of water-dispersible carbon black for fabrication of uranium oxicarbide microspheres. Journal of Nuclear Materials 375: 38–51

    Google Scholar 

  149. Kikuchi T, Tobita T, Ikawa K (1984) Uranium contamination in coating and in matrix material of unirradiated coated particle fuel. Journal of Nuclear Science and Technology 21: 233–242

    Google Scholar 

  150. Kurata Y, Ikawa K, Iwamoto K (1981) Fission product release from TRISO-coated uranium dioxide particles at 1940 to 2320 DegC. Journal of Nuclear Materials 98: 107–115

    Google Scholar 

  151. Lee J-H, Shim J-B, Kim E-H, Yoo J-H, Park S-W, Snyder CT (2008) A feasibility study for the development of alternative methods to treat a spent TRISO fuel. Nuclear Technology 162: 250–258

    Google Scholar 

  152. Lobach SY, Knight TW, Jacob NP, Athon CE (2007) Advanced TRISO fuels with zirconium carbide for high temperature reactors. Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID, United States, Sept 9–13, 2007: 9–14

    Google Scholar 

  153. Long EL, Jr., Tiegs TN, Robbins JM, Kania MJ (1981) Performance of HTGR biso-and triso-coated fertile particles irradiated in capsule HT-34. In. Oak Ridge Natl. Lab., Oak Ridge, TN, USA., p 71

    Google Scholar 

  154. Lopez-Honorato E, Meadows PJ, Xiao P, Marsh G, Abram TJ (2008) Structure and mechanical properties of pyrolytic carbon produced by fluidized bed chemical vapor deposition. Nuclear Engineering and Design 238: 3121–3128

    Google Scholar 

  155. Ogawa T, Fukuda K (1992) Zirconium carbide coated particle fuel development. In. Japan Atomic Energy Res Inst, Tokai, Japan.: 554–560

    Google Scholar 

  156. Pappano PJ, Burchell TD, Hunn JD, Trammell MP (2008) A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP). Journal of Nuclear Materials 381: 25–38

    Google Scholar 

  157. Stansfield OM, Homan FJ, Simon WA, Turner RF (1983) Interaction of fission products and silicon carbide in TRISO fuel particles: a limiting HTGR design parameter. In. GA Technol. Inc., San Diego, CA, USA., p 9

    Google Scholar 

  158. Steward KP (1968) Coating contamination in TRISO fuel particles. In. Gulf Gen. At. Inc., San Diego, CA, USA., p 21

    Google Scholar 

  159. Tan L, Allen TR, Hunn JD, Miller JH (2008) EBSD for microstructure and property characterization of the SiC-coating in TRISO fuel particles. Journal of Nuclear Materials 372: 400–404

    Google Scholar 

  160. Verfondern K, Nabielek H (1985) PANAMA, a computer code to predict TRISO particle failure under accident conditions. In. Kernforschungsanlage Juelich G.m.b.H., Juelich, Fed. Rep. Ger., p 110

    Google Scholar 

  161. Charlier C, Fagerholm R, Slabber J, Shayi JL (2007) Safeguarding the Pebble Bed Modular Reactor: a new challenge for the IAEA. Annual Meeting Proceedings of the Institute of Nuclear Materials Management 48th: 244/241–244/248

    Google Scholar 

  162. Dardour S, Nisan S, Charbit F (2007) Utilisation of waste heat from GT-MHR and PBMR reactors for nuclear desalination. Desalination 205: 254–268

    Google Scholar 

  163. Gittus JH (1999) The ESKOM pebble bed modular reactor. Nuclear Energy (British Nuclear Energy Society) 38: 215–221

    Google Scholar 

  164. Greene CA, Muscara J, Srinivasan M (2003) Materials research needs for advanced reactors. In. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, USA., pp 85–96

    Google Scholar 

  165. Greyvenstein R, Correia M, Kriel W (2008) South Africa's opportunity to maximise the role of nuclear power in a global hydrogen economy. Nuclear Engineering and Design 238: 3031–3040

    Google Scholar 

  166. Hevia F, Slabber J (2005) Pebble bed modular reactor. Nuclear Espana 255: 26–30

    Google Scholar 

  167. Ion S, Nicholls D, Matzie R, Matzner D (2003) Pebble Bed Modular Reactor, the first generation IV reactor to be constructed. World Nuclear Association Annual Symposium: No pp given

    Google Scholar 

  168. Kemm K (1999) Development of the South African Pebble Bed Modular Reactor system. Uranium Institute Annual International Symposium [online computer file] 24th: No pp given

    Google Scholar 

  169. Koster A, Matzie R, Matzner D (2004) Pebble-bed modular reactor: a generation IV high-temperature gas-cooled reactor. Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 218: 309–318

    Google Scholar 

  170. Koster A, Matzner HD, Nicholsi DR (2003) PBMR design for the future. Nuclear Engineering and Design 222: 231–245

    Google Scholar 

  171. McLaughlin DF, Paletta SA, Lahoda EJ, Kriel W, Nigra MM, McLaughlin GT (2005) Hydrogen costs for the PBMR thermal reactor and the westinghouse process. AIChE Annual Meeting, Conference Proceedings, Cincinnati, OH, United States, Oct 30–Nov 4, 2005: 581b/581–581b/521

    Google Scholar 

  172. Nicholls DR (1997) The pebble bed modular reactor. Nuclear Engineer (Institution of Nuclear Engineers) 38: 105–107

    Google Scholar 

  173. Nicholls DR (2000) Status of the pebble bed modular reactor. Nuclear Energy (British Nuclear Energy Society) 39: 231–236

    Google Scholar 

  174. Nicholls DR (2002) Small nuclear reactors: the PBMR. Energia (Madrid, Spain) 166: 35–40

    Google Scholar 

  175. Nicholls DR (2002) The pebble bed modular reactor. South African Journal of Science 98: 31–35

    Google Scholar 

  176. Reitsma F (2004) The pebble bed modular reactor layout and neutronics design of the equilibrium cycle. PHYSOR-2004, Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, IL, United States, Apr 25–29, 2004: 96100/96101–96100/96111

    Google Scholar 

  177. Rubin O, Venter M, Jordaan J (2006) The control of the PBMR nuclear power unit. Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, Embedded Topical Meeting, Reno, NV, United States, June 4–8, 2006: 139–144

    Google Scholar 

  178. van der Merwe JJ, Venter JH (2006) HTR fuel design, qualification and analyses at PBMR. PHYSOR-2006: Advances in Nuclear Analysis and Simulation, American Nuclear Society's Topical Meeting on Reactor Physics, Vancouver, BC, Canada, Sept 10–14, 2006: c021/021–c021/010

    Google Scholar 

  179. Walter A, Schulz A, Lohnert G (2006) Comparison of two models for a pebble bed modular reactor core coupled to a Brayton cycle. Nuclear Engineering and Design 236: 603–614

    Google Scholar 

  180. Alberstein D (1997) Weapons grade plutonium destruction in the gas turbine modular helium reactor (GT-MHR). NATO ASI Series, Series 1: Disarmament Technologies 15: 135–146

    Google Scholar 

  181. Alberstein D, Neylan AJ (1996) Plutonium disposition in the gas turbine modular helium reactor (GT-MHR). ICONE-4, Proceedings of the ASME/JSME International Conference on Nuclear Engineering, 4th, New Orleans, Mar 10–14, 1996 4: 535–547

    Google Scholar 

  182. Baxi CB, Shenoy A, Kostin VI, (2008) Evaluation of alternate power conversion unit designs for the GT-MHR. Nuclear Engineering and Design 238: 2995–3001

    Google Scholar 

  183. Gorelov IN, Kiryushin AI, Kodochigov NG, Kuzavkov NG, Sukharev YP (1998) The gas turbine-modular helium reactor (GT-MHR) for electricity generation and plutonium consumption. Atomic Energy (New York)(Translation of Atomnaya Energiya) 83: 877–881

    Google Scholar 

  184. Kodochigov NG, Kuzavkov NG, Sukharev YP, Ghudin AG, Shenoy AS (1998) The gas turbine-modular helium reactor program for efficient disposition of weapons plutonium. In. OKBM, N. Novgorod, Russia, pp 81–91

    Google Scholar 

  185. La Bar MP, Simon WA (1997) The modular helium reactor for the twenty-first century. Uranium and Nuclear Energy 22nd: 47–58

    Google Scholar 

  186. LaBar MP, Shenoy AS, Simon WA, Campbell EM (2004) The gas-turbine modular helium reactor. Nuclear Energy (British Nuclear Energy Society) 43: 165–175

    Google Scholar 

  187. Lecomte M, Bandelier P (2003) Desalinated water production optimisation using a high temperature reactor in a cogeneration mode. International Journal of Nuclear Desalination 1: 95–103

    Google Scholar 

  188. Lee K-H, Kim K-S, Noh J-M, Zee S-Q (2006) IAEA GT-MHR benchmark calculations using the HELIOS/MASTER code package. PHYSOR-2006: Advances in Nuclear Analysis and Simulation, American Nuclear Society's Topical Meeting on Reactor Physics, Vancouver, BC, Canada, Sept 10–14, 2006: b082/081–b082/089

    Google Scholar 

  189. McDonald CF, Silady FA, Wright RM, Kretzinger KF, Haubert RC (1994) GT-MHR helium gas turbine power conversion system design and development. Proceedings of the American Power Conference 56: 518–523

    Google Scholar 

  190. Neylan AJ, Shenoy A, Silady FA, Dunn TD (1995) GT-MHR design, performance and safety. In. General Atomics, San Diego, CA, USA., pp 136–147

    Google Scholar 

  191. Neylan AJ, Simon WA (1996) Status of the GT-MHR. JAERI-Conf 96-010: 89–96

    Google Scholar 

  192. Ohashi K, Okamoto F, Hayakawa H (2000) Modular high temperature reactor (Modular HTR) contributing the global environment protection. Progress in Nuclear Energy 37: 307–312

    Google Scholar 

  193. Palmer DJ, Kumar S (2005) The helium reactor and fuel cell combined cycle. Nuclear Future 1: 57–60

    Google Scholar 

  194. Penfield SR, Jr., Pause GR, Burger JM, Zugibe KJ (1994) Economic potential of the gas turbine modular helium reactor. Proceedings of the American Power Conference 56: 59–64

    Google Scholar 

  195. Rodriguez C, Zgliczynski J, Pfremmer D (1995) GT-MHR operations and control. In. Neth., pp 159–172

    Google Scholar 

  196. Silberstein AJ (1998) The Gas Turbine Modular Helium Reactor. An international project to develop a safe, efficient, flexible product. In. Framatome, Paris La Defense, Fr., pp 93–102

    Google Scholar 

  197. Talamo A (2006) Advanced in-core fuel cycles for the gas turbine-modular helium reactor. Ph.D. thesis, KTH Royal Institute of Technology, Stockholm, Sweden, p 219

    Google Scholar 

  198. Talamo A (2006) Studies on the feasibility of the LWRs waste-thorium in-core fuel cycle in the gas turbine-modular helium reactor. Journal of Nuclear Science and Technology (Tokyo, Japan) 43: 1379–1394

    Google Scholar 

  199. Talamo A, Gudowski W (2005) Performance of the gas turbine-modular helium reactor fueled with different types of fertile TRISO particles. Annals of Nuclear Energy 32: 1719–1749

    Google Scholar 

  200. Zgliczynski JB, Silady FA, Neylan AJ (1994) The gas turbine-modular helium reactor (GT-MHR), high efficiency, cost competitive, nuclear energy for the next century. Proc Int Top Meet Adv React Saf 2: 628–635

    Google Scholar 

  201. Weil J (November 2001) Pebble-bed design returns. IEEE Spectrum, 37–40

    Google Scholar 

  202. Kodochigov N, Sukharev Yu, Marova E, Ponomarev-Stepnoy N, Glushkov E, Fomichenko P (2003) Neutronic features of the GT-MHR reactor. Nuclear Engineering and Design 222(2–3): 161–171

    Google Scholar 

  203. Ballot B (2002) Presentation of the present HTR concepts and large associated facilities, HTR/ECS 2002 High Temperature Reactor School, Cadarache, France, November 4–8, 2002

    Google Scholar 

  204. Takizuka T (2004) Reactor technology development under the HTTR project. The 1st COE-INES International Symposium, INES-1, Tokyo, Japan, October 31–November 4, 2004

    Google Scholar 

  205. Takamatsu K, Nakagawa S, Takeda T (2006) Development of core dynamics analysis of coolant flow reduction tests of HTTR. Proceedings HTR2006: 3rd International Topical Meeting on High Temperature Reactor Technology, Johannesburg, South Africa, October 1–4, 2006, Paper No. C00000174

    Google Scholar 

  206. Energy Information Administration (2002) Form RW-859, “Nuclear Fuel Data”

    Google Scholar 

  207. OECD/NEA 2006 Nuclear Energy Data, Nuclear Eng. International handbook 2007

    Google Scholar 

  208. World Nuclear Association, London, UK. OECD/NEA 2006 Nuclear Energy Data, Nuclear Eng. International handbook 2007

    Google Scholar 

  209. Uranium Information Centre Limited, Transport of Radioactive Materials, Nuclear Issues Briefing Paper #51, February 2008

    Google Scholar 

  210. 10 CFR 73.26. Transportation physical protection systems, subsystems, components, and procedures. http://www.nrc.gov/reading-rm/doc-collections /cfr/part073/part073-0026.html

  211. U.S. Department of Energy, Science and Technology (2003) Report to Congress on Advanced fuel cycle initiative: the future path for advanced spent fuel treatment and transmutation research

    Google Scholar 

  212. Benedict M, Pigford T, Wolfgang L (1981) Nuclear Chemical Engineering. 2nd Ed. McGraw-Hill, New York

    Google Scholar 

  213. Pigford TH (1974) Environmental aspects of nuclear energy production. Ann Rev Nucl Sci 24: 515–557

    Google Scholar 

  214. Choppin GR, Khankhasayev M (1999) Chemical Separation Technologies and Related Methods of Nuclear Waste Management. Kluwer, Dordrecht: 1–16

    Google Scholar 

  215. Cairns RC (1964) Recovering of spent nuclear fuels: processing. Atomic Power: 57–77

    Google Scholar 

  216. Finsterwalder L (1975) Reprocessing technology. In Ges Wiederaufarbeit Kern-brennstoffen mbH, Eggenstein-Leopoldshafen, Fed Rep Ger: 12

    Google Scholar 

  217. Geier RG (1979) Purex process solvent: literature review. In Rockwell Hanford Operations, Rockwell Int Corp, Richland, WA, USA: 185

    Google Scholar 

  218. Huppert KL (1977) Present state of reprocessing. In Ges Wiederaufarbeitung Kern-brennst mbH, Eggenstein-Leopoldshafen, Fed Rep Ger: 24

    Google Scholar 

  219. Mailen JC (1981) Interpretation of the extraction mechanism of the Purex and Thorex processes from kinetics data. Separation Science and Technology 16: 1373–1387

    Google Scholar 

  220. McKibben JM (1984) Chemistry of the Purex process. Radiochimica Acta 36: 3–15

    Google Scholar 

  221. Beary MM (1970) Solvent improvement resulting from the use of NPH [normal paraffin hydrocarbon mixture] in the Hanford Purex plant. In Atl Richfield Hanford Co, Richland,WA, USA: 9

    Google Scholar 

  222. Bray LA (1967) Recovery of cesium from Purex alkaline waste with a synthetic zeolite. In Battelle-Northwest, Richland, WA, USA: 16

    Google Scholar 

  223. Chaugule GA, Singh RK, Gurba PB, Bajpai DD, Shukla JP, Sundaresan M (1995) Application of sequential solvent extraction process for the removal of major actinides from acidic high-level liquid waste. NUCAR 95: Proceedings of Nuclear and Radio-chemistry Symposium, Kalpakkam, India, February 21–24:158–159

    Google Scholar 

  224. Ertel D (1976) Equipment and instrumentation of a laboratory for Purex process analytical chemistry. Des Equip Hot Lab, Proc Symp: 159–164

    Google Scholar 

  225. Godfrin J, Mousty F, Planson J, Toussaint J (1980) Separation scheme for high-level nuclear effluent actinides. OXAL process. In CCE, Ispra, Italy: 225–245

    Google Scholar 

  226. Gupta KK, Thomas G, Kulkarni PG, Varadarajan N, Singh RK (1995) Evaluation of Duolite S-861 resin for the removal of dissolved TBP from aqueous PUREX process streams. Part II. NUCAR 95: Proceedings of Nuclear and Radiochemistry Symposium, Kalpakkam, India, February 21–24, 1995: 198–199

    Google Scholar 

  227. Henrich E, Bauder U, Marquardt R, Druckenbrodt WG, Wittmann K (1986) A new concept for product refining in the Purex process. Atomkernenergie/Kerntechnik 48: 241–245

    Google Scholar 

  228. Horner DE (1969) Use of ferrous nitrate as a plutonium reductant for partitioning plutonium and uranium in Purex processes. In Oak Ridge Nat Lab, Oak Ridge, TN, USA: 17

    Google Scholar 

  229. Horwitz EP, Kalina DG, Diamond H, Vandegrift GF, Schulz WW (1985) The TRUEX process — a process for the extraction of the transuranic elements from nitric acid wastes utilizing modified PUREX solvent. Solvent Extraction and Ion Exchange 3: 75–109

    Google Scholar 

  230. Itoh Y, Kamei K, Hotoku S, Asakura T, Mineo H, Uchiyama G (2002) Development of solvent washing process using butylamine compounds. JAERI-Conf 2002-004: 603–608

    Google Scholar 

  231. Jackson RR, Walser RL (1977) Purex process operation and performance, 1970 Thoria Campaign. In Atl Richfield Hanford Co, Richland, WA, USA: 194

    Google Scholar 

  232. Kaneko H, Muramoto H, Takeda H, Hoshino T, Segawa T (1980) Iodine removal in the Purex reprocessing process. Fast React Fuel Reprocess, Proc Symp: 185–194

    Google Scholar 

  233. Katoh N, Kiyose R, Yamamoto Y (1975) Multivariable cascade control of the Purex process. Journal of Nuclear Science and Technology 12: 53–60

    Google Scholar 

  234. Kumar S, Koganti SB (2002) Simulation study of tritium extraction behaviour in PUREX process. In Indira Gandhi Centre for Atomic Research, Tamil Nadu, India: 1–17

    Google Scholar 

  235. Kumar SV, Nadkarni MN, Ramanujam A, Venkatesan M, Gopalakrishnan V, Kazi JA (1974) Tail end purification of uranium in the purex process. In Fuel Reprocess Div, Bhabha At Res Cent, Bombay, India: 11

    Google Scholar 

  236. Mendel JE (1965) Laboratory studies on the use of uranium(IV) as a plutonium reduc-tant in a Purex process. United States Atomic Energy Commission [Unclassified and Declassified Reports Published by the Atomic Energy Commission and Its Contractors] HW-82103: 13 pp

    Google Scholar 

  237. Mineo H, Uchiyama G, Hotoku S, Asakura T, Kihara T (1999) Spent fuel test of an advanced PUREX process: PARC. Global ′99: “Nuclear Technology – Bridging the Millennia”, Proceedings of the International Conference on Future Nuclear Systems, Jackson Hole, WY, United States, Aug: 725–731

    Google Scholar 

  238. Navratil JD, Leebl RG (1978) Modified Purex process for the separation and recovery of plutonium-uranium residues. In Rocky Flats Plant, At Int Div, Golden, CO, USA: 19

    Google Scholar 

  239. Ojima H (2008) Outline of the nuclear fuel cycle. In Nuclear Fuel Cycle Engineering Laboratories, Tokai Research and Development Center, Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken, Japan: 1–28

    Google Scholar 

  240. Petrich G (1983) Computer-simulation of the PUREX process. Nukleare Entsorgung 2: 317–332

    Google Scholar 

  241. Petrich G, Kolarik Z (1981) The 1981 Purex distribution data index. In Kernfor-schungszent Karlsruhe GmbH, Karlsruhe, Fed Rep Ger: 108

    Google Scholar 

  242. Rainey RH (1965) Hydrogen reduction of Pu(IV) to Pu(III). Nuclear Applications & Technology 1: 310–311

    Google Scholar 

  243. Ramaniah MV, Rao CL, Pisharody KPR, Jadhav AV, Vishwanatha A (1967) Laboratory studies on the use of uranium(IV) in the Purex process. II. Use of uranium(IV) as the reductant for plutonium. Proc Nucl Radiat Chem Symp, 3rd: 343–350

    Google Scholar 

  244. Ramaniah MV, Rao CL, Pisharody KPR, Jadhav AV, Viswanatha A (1967) Laboratory studies on the use of uranium(IV) in the Purex process. I. Preparation of uranium(IV) solutions. Proc Nucl Radiat Chem Symp, 3rd: 335–342

    Google Scholar 

  245. Richardson GL, Swanson JL (1975) Plutonium partitioning in the Purex process with hydrazine-stabilized hydroxylamine nitrate. In Hanford Eng Dev Lab, Richland, WA, USA: 92

    Google Scholar 

  246. Sakurai S, Nakajima K, Tachimori S (1995) Feasibility study of utilization of organic diluent containing boron in Purex process. Proceedings of the International Conference on Nuclear Criticality Safety, 5th, Albuquerque, Sept 17–21, 1995 2: 7 22–27 27

    Google Scholar 

  247. Salomon L, Eschrich H, Humblet L (1976) Treatment and disposal of tributyl phosphate-kerosene waste by the Eurowatt process. Nucl Energy Maturity, Proc Eur Nucl Conf 8: 224–236

    Google Scholar 

  248. Salomon L, Lopez-Menchero E (1970) Optimization of the aqueous processing of irradiated fuel from nuclear power reactors. Use of uranium(IV) nitrate as reductant in a Purex type processing plant. Industrial & Engineering Chemistry Process Design and Development 9: 345–358

    Google Scholar 

  249. Sawant RM, Rastogi RK, Chaudhuri NK (1998) Study of the extraction of U(IV) relevant to PUREX process. Journal of Radioanalytical and Nuclear Chemistry 229: 203–206

    Google Scholar 

  250. Schultz WS (1969) DBBP [dibutylbutyl phosphonate] solvent extraction recovery of neptunium and plutonium from purex 1WW solution. In. Battelle-Northwest, Rich-land, WA, USA: 47

    Google Scholar 

  251. Schulz WW (1967) Trilaurylamine extraction of neptunium and plutonium from Purex process waste. Industrial & Engineering Chemistry Process Design and Development 6: 115–121

    Google Scholar 

  252. Schulz WW (1970) Macroreticular ion exchange resin cleanup of Purex process tri-butyl phosphate solvent. In Atlantic Richfield Hanford Co., Richland, WA, USA: 26

    Google Scholar 

  253. Segawa T (1967) Reprocessing of nuclear fuel in the World and Japan. Genshiryoku Kogyo 13: 17–22

    Google Scholar 

  254. Srinivasan N, Laxminarayanan TS, Balasubramanian GR, Kapoor SC, Ramaniah MV (1968) Studies on the use of uranium(IV) as a reductant for plutonium in purex process. In Fuel Reprocess Div, Bhabha At Res Centre, Bombay, India: 50

    Google Scholar 

  255. Srinivasan N, Laxminarayanan TS, Balasubramanian GR (1968) Use of uranium(IV) as a reductant for plutonium in Purex process. In Bhabha At Res Centre, Bombay, India: 16

    Google Scholar 

  256. Starks JB (1977) Purex process. In. Savannah River Plant, E I DuPont de Nemours and Co., Aiken, SC, USA: 41

    Google Scholar 

  257. Stevenson CE, Paige DM (1967) Research and development on aqueous processing. Reactor and Fuel-Processing Technology 10: 241–252

    Google Scholar 

  258. Stieglitz L, Becker R (1983) Chemical and radiolytic solvent degradation in the PUREX process. Nukleare Entsorgung 2: 333–350

    Google Scholar 

  259. Taylor RJ, Fox OD, Sarsfield MJ, Carrott MJ, Mason C, Woodhead DA, Maher CJ, Steele H, Koltunov VS (2007) Fundamental chemical kinetic and thermodynamic data for Purex process models. Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID, United States, Sept 9–13, 2007: 180–181

    Google Scholar 

  260. Thompson MC (1977) Solvent extraction of enriched uranium fuels at the Savannah River Plant. In. Savannah River Lab, EI duPont de Nemours and Co, Aiken, SC, USA: 21

    Google Scholar 

  261. Uchiyama G, Asakura T, Hotoku S, Fujine S (1997) Long-lived nuclides separation techniques for advancing Purex process. Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, 6th, Singapore, Oct 12–16, 1997: 255–260

    Google Scholar 

  262. Uchiyama G, Mineo H, Asakura T, Hotoku S, Iizuka M, Fujisaki S, Isogai H, Itoh Y, Hosoya N (2002) PARC process as advanced PUREX process. JAERI-Conf 2002-004: 197–204

    Google Scholar 

  263. Uchiyama G, Mineo H, Hotoku S (2000) PARC process for an advanced PUREX process. Progress in Nuclear Energy 37: 151–156

    Google Scholar 

  264. Venkatesan M, Ravi TN, Govindan P, Raman VR (1995) Laboratory studies on restoring solvent in Purex process. NUCAR 95: Proceedings of Nuclear and Radiochemistry Symposium, Kalpakkam, India, Feb 21–24, 1995: 166–167

    Google Scholar 

  265. Wallwork AL, Bothwell P, Birkett JE, Denniss IS, Taylor RJ, May I (2001) The development of chemical flowsheets for an advanced purex process. Solvent Extraction for the 21st Century, Proceedings of ISEC ′99, Barcelona, Spain, July 11–16, 1999 2: 1463–1467

    Google Scholar 

  266. Walser RL (1970) Hanford Purex plant experience with reductants. In Atl Richfield Hanford Co, Richland, WA, USA: 25

    Google Scholar 

  267. Wang J, Chen J (2007) The application of N,N-Dimethyl-3-Oxa-Glutaramic acid (DOGA) in the PUREX process. Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID, United States, September 9–13: 1131–1136

    Google Scholar 

  268. Wilhite RN (1966) Evaluation of commercial n-paraffin mixtures for Purex diluent. In Savannah River Lab, EI duPont de Nemours and Co, Aiken, SC, USA: 7

    Google Scholar 

  269. Zhang A, Hu J, Zhang X, Wang F (2002) Hydroxylamine derivative in the Purex Process. Journal of Radioanalytical and Nuclear Chemistry 253: 107–113

    Google Scholar 

  270. Baumgaertner F (1976) The Purex process for the reprocessing of nuclear fuels with high plutonium content and high burn-up. Kerntechnik (1959–1978) 18: 245–252

    Google Scholar 

  271. Bondin VV, Gavrilov PM, Revenko YuA, Zilberman BYa, Romanovskij VN, Fedorov YuS, Shadrin AYu, Kudryavcev EG, Haperskaja AV (2007) Simplified PUREX process-perspective SNF reprocessing technologie for the plant of the next generation. Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID, United States, Sept 9–13, 2007: 1484–1489

    Google Scholar 

  272. Boudry JC, Miquel P (1974) Adaptation of the Purex process to the reprocessing of fast reactor fuels. In CEN Commis Energ At, Fontenay-aux-Roses Fr: 19

    Google Scholar 

  273. Boudry JC, Miquel P (1974) Adaptation of the Purex process to the reprocessing of fast reactor fuels. Proc Int Solvent Extr Conf 2: 1551–1567

    Google Scholar 

  274. Endo H, Kamiya M, Shinoda Y, Ojima H (1997) Advanced fuel recycle system concept on PUREX process and MOX fuel fabrication. ICONE-5, Proceedings of the International Conference on Nuclear Engineering, 5th, Nice, May 25–29, 1997: 2211/2211–2211/2218

    Google Scholar 

  275. Faugeras P, Bourgesois M, Talmont X (1971) Processing of highly irradiated fuels. Technical situation and future prospects. Purex process and dry process. In CEN Commis Energ At, Fontenay-aux-Roses Fr: 16

    Google Scholar 

  276. Paiva A, Malik P (2004) Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes. Journal of Radioanalytical and Nuclear Chemistry 261(2): 485–496

    Google Scholar 

  277. Laidler JL (2007) GNEP spent fuel processing: waste stream and disposition options. Nuclear Waste technical Review Board Meeting, Washington D.C. May 15, 2007

    Google Scholar 

  278. Vandegrift GF, Regalbuto MC, Aase SB, Arafat HA, Bakel AJ, Bowers DL, Byrnes JP, Clark MA, Emery JW, Falkenberg JR, Lohman AVG, Hafenrichter D, Leonard RA, Pereira C, Quigley KJ, Tsai Y, Vander Pol MH, Laidler JJ (2004) Lab-Scale demonstration of the UREX+ process. Wm′04 Conference, February 29–March 4, 2004, Tucson, AZ WM-4323

    Google Scholar 

  279. Pereira C, Vandegrift GF, Regalbuto MC, Bakel A, Bowers D, Byrnes JP, Clark MA, Emery JW, Falkenberg JR, Hafenrichter L, Krebs JF, Leonard R, Maggos LE, Quigley KJ, Laidler JJ (2006) Preliminary results of the lab- scale demonstration of the UREX+1a process using spent nuclear fuel. 2006 AIChE National Meeting November 15, 2006

    Google Scholar 

  280. Pereira C, Vandegrift GF, Regalbuto MC, Bakel A, Bowers D, Byrnes JP, Clark MA, Emery JW, Falkenberg JR, Hafenrichter L, Krebs JF, Leonard R, Maggos LE, Quigley KJ, Laidler JJ (2006) Preliminary Results of the Lab- Scale Demonstration of the UREX+1a Process Using Spent Nuclear Fuel. 2006 AIChE National Meeting November 15, 2006

    Google Scholar 

  281. Coops MS, Bowersox DF (1984) Nonaqueous processing methods. In Los Alamos Natl Lab, Los Alamos, NM, USA: 12

    Google Scholar 

  282. Coops MS, Sisson DH (1982) The potential of pyroprocessing for partitioning Purex wastes. Radioactive Waste Management 6: 333–347

    Google Scholar 

  283. Amamoto I, Sato K, Terai T (2006) Behavior of FPs and TRU in a fluoride volatility process. Special Publication – Royal Society of Chemistry 305: 578–580

    Google Scholar 

  284. Carr WH, King LJ, Kitts FG, McDuffee WT, Miles FW (1971) Molten-salt fluoride volatility pilot plant. Recovery of enriched uranium from aluminum-clad fuel elements. In Oak Ridge Natl Lab, Oak Ridge, TN, USA: 78

    Google Scholar 

  285. Cathers GI, Carr WH, Lindauer RB, Milford RP, Whatley ME (1958) Recovery of uranium from highly irradiated reactor fuel by a fused-salt fluoride-volatility process. Proceedings of the United Nations International Conference on the Peaceful Uses of Atomic Energy 17: 473–479

    Google Scholar 

  286. Chijiya M (1976) Studies on fluoride volatility process for the reprocessing of LMFBR fuels. In Sci Technol Agency, Tokyo, Japan: 3

    Google Scholar 

  287. Corbin O, Vanderchmitt A, Lucas M (1980) Ruthenium in fuel reprocessing by fluoride volatility process. (II). Ruthenium species appearing in fluorination step as identified by thermochromatography and IR measurements. Journal of Nuclear Science and Technology 17: 443–447

    Google Scholar 

  288. Dem'yanovich MA, Prusakov VN, Skiba OV (1982) Fluorination of irradiated uranium-plutonium oxide fuel in the flame reactor. In Nauchno-Issled Inst At Reakt, Dimitrovgrad, USSR: 12

    Google Scholar 

  289. Holmes JT, Stethers H, Barghusen JJ (1965) Engineering development of a fluid-bed fluoride volatility process. II. Pilot-scale studies. Nuclear Applications & Technology 1: 301–309

    Google Scholar 

  290. Jonke AA (1968) Development of volatility processes for thermal and fast reactor fuels. In Argonne Nat Lab, Argonne, IL, USA: 65–78

    Google Scholar 

  291. Levitz NM (1968) Fluoride volatility processes-fluorination of uranium and plutonium. In Argonne Nat Lab, Argonne, IL, USA: 18–41

    Google Scholar 

  292. Matsuda M, Sato N, Kirishima A, Tochiyama O (2007) Fluorination behavior of UO2F2 in the presence of F2 and O2. Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID, United States, September 9–13:1474–1476

    Google Scholar 

  293. Mecham WJ, Liimatainen RC, Kessie RW, Seefeldt WB (1957) Decontamination of irradiated uranium by fluoride volatility process. Chem Eng Progr 53: 72F–77F

    Google Scholar 

  294. Reas WH (1967) Fluoride volatility processes. Application to commercial nuclear fuel recovery. In Gen Elec Co, Santa Clara, CA, USA: 342–360

    Google Scholar 

  295. Schmets J (1970) Reprocessing of spent nuclear fuels by fluoride volatility processes. Atomic Energy Review 8: 3–126

    Google Scholar 

  296. Shimada S, Okumura I, Higashi K (1973) Experimental study on fluoride volatility process for thorium fuels. Journal of Nuclear Science and Technology 10: 689–695

    Google Scholar 

  297. Standifer RL (1970) Fluidized-bed fluoride volatility pilot plant for plutonium purification. Chemical Engineering Progress, Symposium Series 66: 198–207

    Google Scholar 

  298. Thompson MA, Marshall RS, Standifer RL (1969) Pilot plant experience on volatile fluoride reprocessing of plutonium. In Rocky Flats Div, Dow Chem Co, Golden, CO, USA: 163–176

    Google Scholar 

  299. Fukasawa T, Umehara H, Matsuda M (2001) Nuclear fuel cycle technology for a long-term stable supply of energy. Hitachi Review 50(3): 89–94

    Google Scholar 

  300. National Research Council (1996) Nuclear Wastes, Technologies for Separations and Transmutation, Appendix D. National Academy Press, Washington DC

    Google Scholar 

  301. Chang YI (2002) Advanced nuclear system for the 21st century. US-Japan Workshop: Nuclear Energy in a New Era, Washington D. C., April 29–30, 2002

    Google Scholar 

  302. Akabori M, Hayashi H, Minato K (2005) Pyrochemical properties of actinides elements. Japan Atomic Energy Research Institute. http://typhoon.jaea.go.jp/nucef2005/ abstracts/S4_R1-2-akabori.pdf

  303. Inoue T (2002) Actinide recycling by pyro-process with metal fuel FBR for future nuclear fuel cycle system. Progress in Nuclear Energy 40(3–4): 547–554

    Google Scholar 

  304. Kinoshita K, Inoue T, Fusselman S, Grimmett DL, Krueger CL, Storvick S (2003) Electrodeposition of uranium and transuranic elements onto solid cathode in LiCl-KCl/Cd system for pyrometallurgical partitioning. Journal of Nuclear Science and Technology 40(7): 524–530

    Google Scholar 

  305. Usami T, Kurata M, Inoue T, Sims HE, Beetham SA, Jenkins JA (2002) Pyrochemical reduction of uranium dioxide and plutonium dioxide by lithium metal. Journal of Nuclear Materials 300(1): 15–26

    Google Scholar 

  306. Nawada H, Fukuda K (2005) Role of pyro-chemical processes in advanced fuel cycles. Journal of Physics and Chemistry of Solids 66: 647–651

    Google Scholar 

  307. Zabunoglu OH, Akbas T (2003) Flow sheet calculations in Thorex method for reprocessing Th-based spent fuels. Nuclear Engineering and Design 219(1): 77–86

    Google Scholar 

  308. Zimmer E, Merz E. Chemical processing of HTR fuels applying either Thorex or Purex flow sheets, IAEA Published Conference Article, http://www.iaea.org/OurWork/ ST/NE/inisnkm/nekr/htgr/fulltext/iwggcr8_ 26.pdf

  309. Le Brun C (2007) Molten salts and nuclear energy production. Journal of Nuclear Materials 360(1): 1–5

    Google Scholar 

  310. International Atomic Energy Agency (1999) Minimization of waste from uranium purification, enrichment and fuel fabrication. IAEA-TECDOC-1115

    Google Scholar 

  311. Frost S (1998) Waste Management in the uranium mining industry. The Uranium Institute 23rd Annual International Symposium, London

    Google Scholar 

  312. Diehl P (2004) Uranium mining and milling wastes: An introduction, WISE Uranium Project

    Google Scholar 

  313. U.S. Environmental Protection Agency, Technical Resource Document (1995) Extraction and beneficiation of ores and minerals 5: Uranium

    Google Scholar 

  314. International Atomic Energy Agency (2004) Treatment of liquid effluent from uranium mines and mills. IAEA-TECDOC-1419, Report of a Coordinated Research Project 1996–2000

    Google Scholar 

  315. Ozawa M, Koma Y, Nomura K, Tanaka Y (1998) Separation of actinides and fission products in high-level liquid wastes by the improved TRUEX process. Journal of Alloys and Compounds 271–273: 538–543

    Google Scholar 

  316. Law J, Herbst R, Todd T (2002) Integrated AMP-PAN, TRUEX, and SREX testing. II. Flowsheet testing for separation of radionuclides from actual acidic radioactive waste. Separation Science and Technology 37(6): 1353–1373

    Google Scholar 

  317. Noyes R (1995) Nuclear Waste Cleanup Technology and Opportunities. Noyes Publications

    Google Scholar 

  318. Law JD, Brewer KN, Herbst RS, Todd TA, Wood DJ (1999) Development and demonstration of solvent extraction processes for the separation of radionuclides from acidic radioactive waste. Waste Management 19(1): 27–37

    Google Scholar 

  319. US Department Energy, Office of Science and Technology (1998) TRUEX/SREX demonstration: Innovative technology summary report. DOE/EM-0419

    Google Scholar 

  320. Todd TA, Law JD, Herbst RS, Meikrantz DH, Peterman DR, Riddle CL, Tillotson RD (2005) Advanced technologies for the simultaneous separation of cesium and strontium from spent nuclear fuel. WM-5083, Waste Management 2005 Conference February 27–March 3 Tucson AZ

    Google Scholar 

  321. Swanson J, Pereira C, Vandegrift GF (2002) Preliminary evaluation of solvent-extraction and/or ion-exchange process for meeting aaa program multi-tier systems recovery and purification goals. Argonne National Lab ANL-02/29

    Google Scholar 

  322. Madic C (2001) Overview of the hydrometallurgical and pyro-metallurgical processes studied worldwide for the partitioning of high active nuclear wastes. Transactions of the 6th International Exchange Meeting, “Actinides and Fission Product Partitioning and Transmutation”, Madrid, Spain, December 11–13, 2000

    Google Scholar 

  323. Pereira C, Vandegrift GF, Regalbuto MC, Bakel A, Bowers D, Byrnes JP, Clark MA, Emery JW, Falkenberg JR, Hafenrichter L, Leonard R, Quigley KJ, VanderPol MH, Laidler JJ (2005) Preliminary results of the lab-scale demonstration of the UREX+1a process using spent nuclear fuel. 2005 AlChE National Meeting, November 3

    Google Scholar 

  324. Logsdail DH, Mills AL (Eds) (1985) Solvent Extraction and Ion Exchange in the Nuclear Fuel Cycle. Society of Chemical Industry, Ellis Horwood, Chichester

    Google Scholar 

  325. Ojovan M, Lee W (2005) An Introduction to Nuclear Waste Immobilisation. Elsevier, Oxford

    Google Scholar 

  326. Thomasson J, Barithel S, Cocaud A, Derycke P, Pierre P (2003) The Universal canister strategy in spent fuel reprocessing: UC-C a real industrial improvement. WM′ 03 Conference, February 23-27, 2003, Tucson, AZ. http://www.wmsym.org/abstracts/ 2003/194.pdf

  327. cermet nuclear fuels designed for the transmutation of transuranic isotopes, materials science forum 561–565: 1733–1736

    Google Scholar 

  328. Nuttall W (2005) Nuclear Renaissance Technologies and Policies for the Future of Nuclear Power. Institute of Physics Publishing, Bristol

    Google Scholar 

  329. Chang YI (2002) Advanced nuclear system for the 21st century. US–Japan Workshop: Nuclear Energy in a New Era, Washington D. C., April 29–30, 2002

    Google Scholar 

  330. Schenkel R, Magill J, Glatz J-P, Mayer K (2003) Partitioning and Transmutation – Technical Feasibility, Proliferation Resistance and Safeguardability, IAEA-SM-367/15/03

    Google Scholar 

  331. World Nuclear Association, Accelerator-driven nuclear energy. http://www.world-nuclear.org/info/inf35.html

  332. Gudowski W, Why accelerator driven transmutation of wastes enable future nuclear power http://www.neutron.kth.se/publications/conference_papers/W_Gudowski_FR202_1.P DF. 12/14/2008

    Google Scholar 

  333. Moncouyoux J, Nabot J (2002) Waste vitrification: More than one string to its bow. Nuclear Energy Division, Commissariat a l'Energie Atomique, CLEFS CEA No 46, Spring, 2002 http://www.cea.fr/var/cea/storage/static/gb/library/Clefs46/pdfg/14-wastevitrification.pdf

    Google Scholar 

  334. Hamel WF, Jr., Valenti PJ, Elliott DI (1999) Completion of the first phase of HLW vitrification at the west valley demonstration project. WM'99 Conference, February 28–March 4, 1999

    Google Scholar 

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(2009). Nuclear. In: Ghosh, T.K., Prelas, M.A. (eds) Energy Resources and Systems. Springer, Dordrecht. https://doi.org/10.1007/978-90-481-2383-4_9

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