BEHAVIOR OF TRITIUM IN THE PUREX PROCESS

REFERENCES

• N.D. Dudey , Review of low-mass atom production in fast reactors, , ANL-7473 ( 1968 ).
   Google Scholar
• A. Bleir , R. Krobel , K.H. Neeb , E. Schneider , Tritium inventories and behavior in zircaloy cladding of spent light water reactor rods, Proceedings of International Meeting on Fuel Reprocessing and Waste Management ,( 1984 ).
   Google Scholar
• H. Brucher , Management methods for the radio nuclides tritium, carbon-14 and krypton-85 arising from reprocessing , Proceedings of International Conference on Radioactive Waste Management , Can. Nucl. Soc. , ( 1982 ) 416 .
   Google Scholar
• H. Schnez , M. Laser , and E. Merz , GERHTR-139( , 1974 ).
   Google Scholar
• Nuclear Energy Agency, Radiological significance and management of tritium, carbon-14, krypton-85 and iodine-129 arising from the nuclear fuel cycle,OECD, , Paris ( 1980 ).
   Google Scholar
• J.H. Goode , Voloxidation removal of volatile fission products from spent LMFBR fuels, , ORNL-TM-3723 ( 1973 ).
   Google Scholar
• W.S. Groenier , Current position and status of the voloxidation process at ORNL, , ORNL/CF-77/67 ( 1977 ).
   Google Scholar
• H.A.C. Mckay , Tritium immobilisation, , Eur. Appl. Res. 1 . 3 ( 1979 )599.
   Google Scholar
• H. Evers , H. Harberl and H.D. Behrnens , Tritium and zirconium separation from PUREX process solutions, Proceedings of International Conference on Nuclear Fuel, Reprocessing and Waste Management ,( 1987 ).
   Google Scholar
• G. Uchiyama , M. Kitamura , K. Yamazaki , S. Sugikawa , M. Maeda and T. Tsujino , Study on voloxidation process for tritium control in reprocessing , Radioactive Waste Management and the Nuclear Fuel Cycle, , 17 , 63 ( 1992 ).
   Google Scholar
• M. Maeda , S. Fujine , S. Sugikawa , G. Uchiyama , T. Tsujino , H. Ai , N. Okabe , Y. Ohtou , N. Suyama , and S. Sato , Tritium scrubbing of organic stream from co-decontamination step for tritiated water recycle process , Proceedings of International Conference on Nuclear Fuel, Reprocessing and Waste Management, , 511 ( 1987 ).
   Google Scholar
• S. Fujine , G. Uchiyama , M. Maeda , H. Bautz and L. Stieglitz , Solvent Extraction 1990 , Elsevier Science Publishers , Part A, 549 ( 1993 ).
   Google Scholar
• W. Davis , Jr., Nucl. Sci. Eng., , 14 , 159 ( 1962 ).
   Web of Science ®Google Scholar
• D.W. Tedder and W. Davis Jr., Solvent Extr.Ion Exch. , 11 ( 1983 ).
   Google Scholar
• S.B. Watson and R.H. Rainey, , ORNL-TM-5123 ( 1975 ).
   Google Scholar
• A.H. Stollenwerk , M. Weishaupt , L. Stieglitz , R. Becker , Safety of the Nuclear Fuel Cycle, , VCH Verlagsgesellschft , Germany , 85 ( 1989 ).
   Google Scholar
• S. Fujine , G. Uchiyama , S. Sugikawa , M. Maeda and T. Tsujino , JAERI-M 89 – 172 [in Japanese] .
   Google Scholar