Recovering and recycling uranium used for production of molybdenum-99

Reilly, Sean Douglas; May, Iain; Copping, Roy; Dale, Gregory Edward

Title: Recovering and recycling uranium used for production of molybdenum-99

Patent · Tue Dec 12 00:00:00 EST 2017

OSTI ID:1413208

Reilly, Sean Douglas; May, Iain; Copping, Roy; Dale, Gregory Edward

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

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Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE

DOE Contract Number:: AC52-06NA25396

Assignee:: Los Alamos National Security, LLC (Los Alamos, NM)

Patent Number(s):: 9,842,664

Application Number:: 14/038,424

OSTI ID:: 1413208

Resource Relation:: Patent File Date: 2013 Sep 26

Country of Publication:: United States

Language:: English

References (40)

Production of High Purity Radioactive Isotopes Lieberman, Ephraim; Gemmill, Wayne J. https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3382152 US Patent Document 3,382,152	patent	May 1968
Production of High Purity Radioactive Technetium-99m Arino, Hirofumi https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3468808 US Patent Document 3,468,808	patent	September 1969
Production of High Purity Molybdenum Using Silver Coated Carbon as Adsorbent Arino, Hirofumi; Madigan, Paul Mylett https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3745119 US Patent Document 3,745,119	patent	July 1973
Production of High Purity Fission Product Molybdenum-99 Arino, Hirofumi; Kramer, Henry H.; McGovern, James J. https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3799883 US Patent Document 3,799,883	patent	March 1974
Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products Hadi, Ali Sameh Abdel; Menzler, Peter-Michael; Reinhardt, Johann https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4093697 US Patent Document 4,093,697	patent	June 1978
Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products Hadi, Ali Sameh Abdel; Reinhardt, Johann; Knapp, Jutta https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4094953 US Patent Document 4,094,953	patent	June 1978
Process for concentrating technetium-99m Laidler, John Barry; Abrahams, Roy https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4176158 US Patent Document 4,176,158	patent	November 1979
Method for enhanced control of radioiodine in the production of fission product molybdenum 99 Pomares, Raul J.; Ruiz, Carl P.; Simpson, Douglas https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4284472 US Patent Document 4,284,472	patent	August 1981
Process for the recovery of molybdenum-99 from an irradiated uranium alloy target Koehly, Gerard; Madic, Charles https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4701308 US Patent Document 4,701,308	patent	October 1987
Method of separating uranium and plutonium from mixed solution containing uranium and plutonium Ohuchi, Jin; Kondoh, Isao; Okada, Takashi https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/5112581 US Patent Document 5,112,581	patent	May 1992
Method of separating fission molybdenum Sameh, Abdel H. A.; Leifeld, Wolfdietrich https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/5508010 US Patent Document 5,508,010	patent	April 1996
Medical isotope production reactor Ball, Russell M. https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/5596611 US Patent Document 5,596,611	patent	January 1997
Method of recovering uranium and transuranic elements from spent nuclear fuel Todokoro, Akio; Kihara, Yoshiyuki; Okada, Takashi https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/6033636 US Patent Document 6,033,636	patent	March 2000
Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization Yano, Kimihiko; Shibata, Atsuhiro; Nomura, Kazunori https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/7011798 US Patent Document 7,011,798	patent	March 2006
Processes for recovering metals from aqueous solutions Bednarski, Troy Allan; Cocalia, Violina Antoneta; Soderstrom, Matthew Dean https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/8328900 US Patent Document 8,328,900	patent	December 2012
Method of producing molybdenum-99 Pitcher, Eric John https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/8450629 US Patent Document 8,450,629	patent	May 2013
Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization Yano, Kimihiko; Shibata, Atsuhiro; Nomura, Kazunori https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20030133860 US Patent Application 10/262863; 20030133860	patent-application	July 2003
Method and Apparatus for the Extraction and Processing of Molybdenum-99 Glenn, Daniel E.; Aase, Scott B.; Stagg, William R. https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20110206579 US Patent Application 13/029332; 20110206579	patent-application	August 2011
Column Geometry to Maximize Elution Efficiencies for Molybdenum-99 Varnedoe, Jennifer; Russell, II, William Earl; Bloomquist, Bradley D. https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20110250107 US Patent Application 12/755714; 20110250107	patent-application	October 2011
Methods Of Separating Medical Isotopes From Uranium Solutions Piefer, Gregory https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20120300891 US Patent Application 13/460033; 20120300891	patent-application	November 2012
Fuel Preparation For Use In The Production Of Medical Isotopes Policke, Timothy; Aase, Scott; Stagg, William https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20140112858 US Patent Application 13/659419; 20140112858	patent-application	April 2014
Recovery Of Uranium From An Irradiated Solid Target After Removal Of Molybdenum-99 Produced From The Irradiated Target Reilly, Sean; May, Iain; Copping, Roy https://doi.org/https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20150085964 US Patent Application 14/042115; 20150085964	patent-application	March 2015
Study on the separation of molybdenum-99 and recycling of uranium to water boiler reactor Cheng, W. L.; Lee, C. S.; Chen, C. C. International Journal of Radiation Applications and Instrumentation. Part A. Applied Radiation and Isotopes, Vol. 40, Issue 4, p. 315-324 https://doi.org/10.1016/0883-2889(89)90224-4	journal	January 1989
Batch Crystallization of Uranyl Nitrate Chikazawa, Takahiro; Kikuchi, Toshiaki; Shibata, Atsuhiro Journal of Nuclear Science and Technology, Vol. 45, Issue 6, p. 582-587 https://doi.org/10.1080/18811248.2008.9711882	journal	January 2012
Improved processes of molybdenum-99 production Dadachova, K.; La Riviere, K.; Anderson, P. Journal of Radioanalytical and Nuclear Chemistry, Vol. 240, Issue 3, p. 935-938 https://doi.org/10.1007/BF02349877	journal	June 1999
The system uranyl sulphate-water—I: Preparation and characterization of the phases in the system Cordfunke, E. H. P. Journal of Inorganic and Nuclear Chemistry, Vol. 31, Issue 5, p. 1327-1335 https://doi.org/10.1016/0022-1902(69)80244-7	journal	May 1969
Flowsheet Study of U-Pu Co-Crystallization Reprocessing System Hommaa, Shunji; Ishii, Jun-ichi; Kikuchi, Toshiaki Journal of Nuclear Science and Technology, Vol. 45, Issue 6, p. 510-517 https://doi.org/10.1080/18811248.2008.9711874	journal	January 2012
Separation of ⁹⁹Mo from a simulated fission product solution by precipitation with a-benzoinoxime Hwang, D. S.; Choung, W. M.; Kim, Y. K. Journal of Radioanalytical and Nuclear Chemistry, Vol. 254, Issue 2, p. 255-262 https://doi.org/10.1023/A:1021659429587	journal	January 2002
Challenges of Extracting and Purifying Fission-Produced Molybdenum-99 McDonald, Marion J.; Carson, Susan D.; Naranjo, Gerald E. Industrial & Engineering Chemistry Research, Vol. 39, Issue 9, p. 3146-3150 https://doi.org/10.1021/ie990377h	journal	September 2000
Crystallization of Uranium Complexes for Partitioning of Spent Nuclear Fuel Mullins, Don; Jarvinen, Gordon; Mayne, Michael Separations for the Nuclear Fuel Cycle in the 21 ^st Century , Vol. 933, Issue Chapter 12, p. 183-197 https://doi.org/10.1021/bk-2006-0933.ch012	book	June 2006
Large scale production of fission ⁹⁹Mo by using fuel elements of a research reactor as starting material Münze, R.; Hladik, O.; Bernhard, G. The International Journal of Applied Radiation and Isotopes, Vol. 35, Issue 8, p. 749-754 https://doi.org/10.1016/0020-708X(84)90081-4	journal	August 1984
Behavior of Actinide Elements and Fission Products in Recovery of Uranyl Nitrate Hexahydrate Crystal by Cooling Crystallization Method Nakahara, Masaumi; Koizumi, Tsutomu; Nomura, Kazunori Nuclear Technology, Vol. 174, Issue 1, p. 109-118 https://doi.org/10.13182/NT11-A11684	journal	April 2011
Effect of crystal size on purity of uranyl nitrate hexahydrate crystalline particles grown in nitric acid medium Nakahara, M.; Nomura, K. Radiochimica Acta, Vol. 100, Issue 11, p. 821-826 https://doi.org/10.1524/ract.2012.1978	journal	November 2012
Enhancement of Decontamination Performance of Impurities for Uranyl Nitrate Hexahydrate Crystalline Particles by Crystal Purification Operation Nakahara, Masaumi; Koizumi, Tsutomu; Nomura, Kazunori Nuclear Technology, Vol. 174, Issue 1, p. 77-84 https://doi.org/10.13182/NT11-A11681	journal	April 2011
Precipitation Behavior of Dicesium Tetravalent Plutonium Hexanitrate in Cooling Crystallization of Uranyl Nitrate Hexahydrate Nakahara, Masaumi; Koizumi, Tsutomu; Nomura, Kazunori Nuclear Technology, Vol. 173, Issue 2, p. 183-190 https://doi.org/10.13182/NT11-A11547	journal	February 2011
Purification Rate of Uranyl Nitrate Hexahydrate Crystal for Transuranium Elements on Isothermal Sweating Phenomenon Nakahara, Masaumi; Nomura, Kazunori; Koizumi, Tsutomu Industrial & Engineering Chemistry Research, Vol. 49, Issue 22, p. 11661-11666 https://doi.org/10.1021/ie1012097	journal	November 2010
Removal of Liquid and Solid Impurities from Uranyl Nitrate Hexahydrate Crystalline Particles in Crystal Purification Process Nakahara, Masaumi; Nomura, Kazunori; Washiya, Tadahiro Journal of Nuclear Science and Technology, Vol. 48, Issue 3, p. 322-329 https://doi.org/10.1080/18811248.2011.9711706	journal	January 2012
Scrambling to Close the Isotope Gap Service, Robert F. Science, Vol. 331, Issue 6015, p. 277-279 https://doi.org/10.1126/science.331.6015.277	journal	January 2011
The isolation of ⁹⁹Mo from fission material for use in the ⁹⁹Mo/^99mTc generator for medical use van der Walt, T. N.; Coetzee, P. P. Radiochimica Acta, Vol. 92, Issue 4-6, p. 251-257 https://doi.org/10.1524/ract.92.4.251.35589	journal	January 2004
Uranium Crystallization Test with Dissolver Solution of Irradiated Fuel Yano, Kimihiko; Shibata, Atsuhiro; Nomura, Kazunori Journal of Nuclear Science and Technology, Vol. 44, Issue 3, p. 344-348 https://doi.org/10.1080/18811248.2007.9711292	journal	January 2012

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