254
Views
21
CrossRef citations to date
0
Altmetric
EXTRACTION

Recent R&D Studies Related to Coprocessing of Spent Nuclear Fuel Using N,N-Dihexyloctanamide

, , &
Pages 3650-3663 | Received 26 Dec 2008, Accepted 10 Jun 2009, Published online: 05 Nov 2009

REFERENCES

  • Knighton , J.B. ; Baldwin , C.E. ( 1979 ) Pyrochemical coprocessing of uranium dioxide-plutonium dioxide LMFBR fuel by the salt transport method . Rocky Flats Report RFP-2887, CONF-790415-29 .
  • Zabunoğlu , O.H. ; Özdemir , L. ( 2005 ) Purex co-processing of spent LWR fuels: Comparative fuel cost analyses . Ann. Nucl. Energy , 32 : 137 .
  • Zabunoğlu , O.H. ; Özdemir , L. ( 2005 ) Purex co-processing of spent LWR fuels: Flow sheet . Ann. Nucl. Energy , 32 : 151 .
  • Pereira , C. ; Leite , E.M. ( 1998 ) Non-proliferating reprocessed nuclear fuels in pressurized water reactors: Fuel cycle options . Ann. Nucl. Energy , 25 : 937 .
  • Pobereskin , M. ; Kok , K.D. ; Madia , W.J. ( 1978 ) Coprocessing – an evaluation of chemical reprocessing without plutonium separation . Nucl. Technol. , 41 : 149 .
  • Sunanta , P. ; Reiner , P. ( 1980 ) Recycling of actinides in light water reactors . Nucl. Technol. , 51 : 7 .
  • Statton , M.A. ; Thompson , M.C. ( 1979 ) Flowsheet for Coprocessing Uranium and Plutonium, USDOE Report, DP-1505 .
  • Baron , P. ; Dinh , B. ; Masson , M. ; Drain , F. ; Emin , J. Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide . World International Patent Organization, Patent No. WO/2007/135178, November 29, 2007 .
  • Vasudeva Rao , P.R. ( 1998 ) Extraction of actinides by trialkyl phosphates . Min. Pro. Ext. Met. Rev. , 18 : 309 .
  • McKay , H.A.C. ; Miles , J.H. ; Swanson , J.L. ( 1990 ) The Purex Process, “Science and Technology of Tributyl Phosphate,” v.3 . In: Applications of Tributyl Phosphate in Nuclear Fuel Reprocessing ; Schulz , W.W. ; Burger , L.L. ; Navratil , J.D. ; Bender , K.P. , eds.; CRC Press Inc. : Boca Raton , Florida .
  • Siddall , T.H. ; Wallace , R.M. (1960) Effect of solvent degradation on the PUREX process. USDOE-Report DP-286.
  • Deshingkar , D.S. ; Ramaswamy , M. ; Kartha , P.K.S. ; Kutty , P.V.E. ; Ramanujam , A. ( 1989 ) Treatment of tributyl phosphate wastes by extraction cum pyrolysis process . Report BARC – 1480 , Bhabha Atomic Research Centre , Mumbai , India .
  • Siddall , T.H. ( 1961 ) Effects of structure of N,N-disubstituted amides on their extraction of actinide and zirconium nitrates and of nitric acid . J. Phys. Chem. , 64 : 1863 .
  • Musikas , C. ( 1987 ) Solvent extraction for the chemical separations of the 5 f elements . Inorg. Chim. Acta , 140 : 197 .
  • Gasparini , G.M. ; Grossi , G. ( 1986 ) Long chain disubstituted aliphatic amides as extracting agents in industrial applications of solvent extraction . Solv. Extr. Ion Exch. , 4 : 1233 .
  • Manchanda , V.K. ; Pathak , P.N. ( 2004 ) Amides and diamides as promising extractants in the back end of the nuclear fuel cycle: An overview . Sep. & Pur. Technol. , 35 : 85 .
  • Miguirditchian , M. ; Sorel , C. ; Camès , B. ; Bisel , I. ; Baron , P. ( 2008 ) Extraction of uranium(VI) by N,N-di-ethyl(2-hexyl)isobutyramide (DEHIBA): From the batch experimental data to counter-current process . ISEC-2008, Tucson, Arizona .
  • Sasaki , Y. ; Suzuki , S. ; Tachimori , S. ; Kimura , T. ( 2003 ) An innovative chemical separation process (ARTIST) for treatment of spent nuclear fuel . Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy, Global 2003 , p. 1266 .
  • Vasudeva Rao , P.R. ; Kolarik , Z. ( 1996 ) A review of third phase formation in extraction of actinides by neutral organophosphorus extractants . Solv. Extr. Ion Exch. , 14 : 955 .
  • Parikh , K.J. ; Pathak , P.N. ; Misra , S.K. ; Tripathi , S.C. ; Dakshinamoorthy , A. ; Manchanda , V.K. ( 2009 ) Radiolytic degradation studies on N,N-dihexyloctanamide (DHOA) under PUREX process conditions . Solv. Extr. Ion Exch. , 27 : 244 .
  • Srinivasan , N. ; Nadkarni , M.N. ; Balasubramanian , G.R. ; Chitnis , R.T. ; Siddiqui , H.R. ( 1972 ) Pilot plant for the separation of U-233 at Trombay . BARC Report-643 , Bhabha Atomic Research Centre , Mumbai , India .
  • Sajun , M.S. ; Ramakrishna , V.V. ; Patil , S.K. ( 1981 ) The effect of temperature on the extraction of plutonium(IV) from nitric acid by tri-n-butyl phosphate . Thermochim. Acta , 47 : 277 .

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.