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INL/EXT-10-17753

Nuclear Fuel Reprocessing

Michael F. Simpson Jack D. Law

February 2010

The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-10-17753

Nuclear Fuel Reprocessing

Michael F. Simpson Jack D. Law

February 2010

Idaho National Laboratory Idaho Falls, Idaho 83415

http://www.inl.gov

Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 3!*# 0 3#* #.0-!#11',%

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Mixing section Settling section

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In , advanced aqueous processing technologies are being developed and assessed to support future recycling of Am and Cm or the minor actinides together with U and Pu to fast reactors. Pilot-scale demonstration is planned within the next decade with a goal of industrial deployment to support the deployment of Generation IV fast reactors. France is also in the process of selecting a site for a geological repository for disposal of high-level waste with a goal to open the repository in 2025. Research related to the study of geological formations and the capacity as a deep geological repository for HLW is being conducted at the Meuse/Haute Marne Underground Research Laboratory located in Bure, France.

Russia is currently processing used fuel from civilian power reactors as well as spent HEU fuel from naval and other reactors at ’s RT-1 aqueous reprocessing plant. The Experimental-Demonstration Center (EDC), which will be a 100 MT/yr pilot facility for evaluation of the fuel cycle based on modified PUREX extraction technology, is currently being designed. This facility will also be used to develop other advanced processing technologies for processing used fuel from thermal reactors. The current goal is to support completion of a new aqueous reprocessing facility around 2025. Research is also actively being performed relative to pyroprocessing technologies for the processing of spent fuel from future fast reactors. To this end, the Multipurpose Pyroprocessing Complex (MPC) is being designed at the Research Institute of Atomic Reactors (RIAR) to support processing development at a capacity of up to 2,500 kg fast reactor used fuel per year.

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1. OECD and IAEA, 2007: Resources, Production, and Demand; Nuclear Energy Agency, June 2008. 2. Gray LW (1999) From separations to reconstitution – A short history of in the US and . Lawrence Livermore National Laboratory, UCRL-JC-133802 3. Evans TF and Tomlinson RE (1954) Hot semiworks studies, Hanford Atomics Products Operations, HW-31767 4. (1951) REDOX technical manual, Hanford Works, HW-18700. 5. Hore-Lacy I (2009) Mixed oxide fuel (MOX). World Nuclear Association (Content Partner); Cutler J. Cleveland (Topic Editor). In: Encyclopedia of Earth. Eds. Cutler J. Cleveland (, D.C.: Environmental Information Coalition, National Council for Science and the Environment). 6. Denniss IS and Jeapes AP (2001)Reprocessing irradiated fuel In: Wilson PD (ed) The : from ore to wastes, Oxford University Press, Oxford, UK, p. 120 7. Poczynajlo A (1988) Studies on reductive back extraction of plutonium in PUREX process. J. Radioanal. Nucl. Chem., vol 125 no.2, p 445-465 8. Long, JT (1967), Engineering for Nuclear Fuel Reprocessing, Gordon Breach Sci. Publ., N.Y.

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T[ 41. Benedict, R.W.; “EBR-II Spent Fuel Treatment Demonstration Project;” Transactions of the American Nuclear Society, vol. 77, pp. 75-76 (1997). 42. Ackerman, J.P.; “Chemical Basis for Pyrochemical Reprocessing of Nuclear Fuel;” Industrial and Engineering Research, vol. 30, N. 1, pp. 141-145 (1991). 43. Lee S.Y. et al. (2007) A Preliminary Study on the Safeguardability of a Korean Advanced Pyroprocessing Facility (KAPF). Proceedings of Global 2007, Boise, Idaho. 44. Lee H.S., Hur J.M., Ahn D.H., Kim I.T., and Lee J.H. (2009) Development of Pyroprocessing Technology at KAERI. Proceedings of Global 2009, Paris, France. 45. Willit J.L., Miller W.E., and Battles J.E. “Electrorefining of Uranium and Plutonium – A Literature Review.” Journal of Nuclear Materials, vol. 195, No. 3, 1992, pp. 229-249. 46. Goff K.M. and Benedict R.W. “Electrorefining Experience for Pyrochemical Reprocessing of Spent EBR-II Fuel.” Proceedings of Global 2005, Tsukuba, Ibaraki (Japan). 47. H 0#** 2TTQ *-30'1& ,) 0 HT5TQ +'2& TTQ &-5 TTQ ," #"#7 T b#. 0 2'-, -$ ,!2','"#1 $0-+ 4 3#* 11',% -*2#,V *2V6 1#" 2*#!20-!&#+'! * 00-!#11#1Tc NuclearTechnologyQ 4-*T SUXQ #!#+ #0 TRRSQ UVTVUWUT 48. Gourishankar K., Redey L., and Williamson M. “Electrochemical Reduction of Metal Oxides in Molten Salts.” Light Metals 2002, TMS. 49. Westphal B.R., Keiser D.D., Rigg R.H., and Laug D.V. “Production of Metal Waste Forms from Spent Fuel Treatment,” Proceedings of the DOE Meeting: Challenges and Initiatives, Salt Lake City, Utah; December 13-16, 1994. 50. Abraham D.P., McDeavitt S.M., and Park J. “Metal Waste Forms from the Electrometallurgical Treatment of Spent Nuclear Fuel.” Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Management, Reno, Nevada, June 16-20, 1996. 51. 0#0#'0 TQ . 1& TTQ #5'1 T,TQ '!&+ ,, THTQ ," 6 1!- T MaterialsResearchSocietySymposiumProceedings WWX S[[[Q SSWT 52. ,&*35 *' THTQ *#7#0 .THTQ 0#0#'0 TQ ," ,!)#0+ , T0T Ind.Eng. Chem.ResT S[[ZQ 37Q SVWT 53. #6 T ," -&,1-, !T F!!*31'-, ," !-, 26!& ,%# ', 2&# -*2#, '2&'3+ &*-0'"#V0-2 11'3+ &*-0'"#V,*) *' &*-0'"#  *2 & I#-*'2# V, 712#+ 5'2& ,*) *' #2 * &*-0'"#1 -$ -"'3+Q 3 '"'3+Q ," #1'3+T MetallurgicalandMaterialsTransactions TRRSQ 32BQ VT[T 54. 0&-,%') 0--, T ," '+.1-,Q T T b 5- '2# 2/3'*' 0'3+ -"#* $-0 !-, 26!& ,%# 6#25##, 3*2'4 *#,2  2'-,1 ," I#-*'2#V, ', -*2#,  *2Rc AIChEJournalQ 5-*T WTQ -T WQ ..T SYUXVSYVUQ  7 TRRXT 55. H'+ 2T.TQ 0 0) *T!TQ &- OTITQ ," O ,% .TT b, #5 ,..0- !& 2- ','+'8# 070-.0-!#11',% 4 12#  *21 &0-3%& #0'#1 -$ '11'-, 00-"3!2 #+-4 * 00-!#11Tc NuclearTechnologyQ 4-*T SXTQ -T TQ TRRZQ ..T TRZVTSZT

UR 56. '+.1-, T T ,"  !&"#4 0T b#4#*-.+#,2 -$ 2*#!20-0#$',#0 4 12#  *2 '1.-1 * 00-!#11 $-0 2&# 26 V!! .#,2 3#* 0# 2+#,2 00-(#!2Rc NuclearEngineeringandTechnologyQ 4-*T VRQ -T UQ ,.0'* TRRZT 57. '+.1-, T TQ *-$$ HTTQ -&,1-, T*TQ 6 2#+ , HTTQ 6 22'12' TTQ -#51 HTTQ 0 ,) TTQ -1!' TTQ ," F_.-**#0 , T0T b, #1!0'.2'-, -$ 2&# #0 +'! 4 12# -0+ 00-"3!2'-, 00-!#11 $0-+ 2&# #+-,120 2'-, 0& 1# -$ 2&# 2*#!20-+#2 **30%'! * 0# 2+#,2 -$ 26 V!! .#,2 3#*Qc NuclearTechnologyQ 4-*TSUVQ ..T TXUVTYY TRRST 58. Thomas J.L.,Mange M., and Eyraud C. Molecular Sieve -I., R.F. Gould, Ed., Amer. Chem. Soc. (1971). 59. Ebert W.E. “Testing to evaluate the suitability of waste forms developed for electrometallurgically treated spent sodium-bonded nuclear fuel for disposal in the Yucca Mountain repository.” Argonne National Laboratory, ANL-05/43, September 2005.

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