Zobrazeno 1 - 10
of 17
pro vyhledávání: '"F.R. Chattin"'
Publikováno v:
Separation Science and Technology. 34:1195-1215
At the Radiochemical Engineering Development Center (REDC), irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste
Publikováno v:
Separation Science and Technology. 30:1769-1778
The Radiochemical Engineering Development Center (REDC) at Oak Ridge National Laboratory (ORNL) processes highly irradiated targets for the Mark 42 program to separate Am, Cm, and Pu. The target feed material for each assembly was 3.3 kg of plutonium
At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d5d023da55bb0d0f27a896b9f1892f4d
https://doi.org/10.2172/564035
https://doi.org/10.2172/564035
Publikováno v:
Transplutonium Elements—Production and Recovery ISBN: 9780841206380
Resin-based loading and calcination techniques have been used to produce all curium and americium oxide feed material (about 2.2 kg) for HFIR targets since 1971. The process based on Dowex 50W resin has progressed from a series of test runs, through
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6bd42b95de2b108aa22ec47af0e2aaf
https://doi.org/10.1021/bk-1981-0161.ch011
https://doi.org/10.1021/bk-1981-0161.ch011
Autor:
J.E. Bigelow, L.J. King, H.C. Savage, R.G. Stacy, E.D. Collins, D.E. Benker, F.R. Chattin, R.G. Ross
A series of five solvent extraction tests were made in the Solvent Extraction Test Facility (SETF) during Campaign 6. Each test used a coprocessing flowsheet that included coextraction-coscrubbing of the heavy metals followed by partial partitioning
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4282afbd8a93d6bf30e9c0fa8e3d613a
https://doi.org/10.2172/712832
https://doi.org/10.2172/712832
Publikováno v:
Transplutonium Elements—Production and Recovery ISBN: 9780841206380
Decigram quantities of highly radioactive transplutonium elements are routinely partitioned at TRU by chromatographic elution from cation resin using AHIB eluent. By using two high-pressure ion exchange columns, a small one for the initial loading of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b98267ec151e05cb72d5afbb92bca23
https://doi.org/10.1021/bk-1981-0161.ch010
https://doi.org/10.1021/bk-1981-0161.ch010
Autor:
F.G. Kitts, L.J. King, D.O. Campbell, R.G. Ross, W.D. Bond, R.G. Stacy, F.R. Chattin, D.E. Benker, J.E. Bigelow
Two solvent extraction experiments were made in the Solvent Extraction Test Facility (SETF) during Campaign 10 to continue the evaluation of: (1) a computer control system for the coextraction-coscrub contractor; and (2) a partitioning technique that
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2fa31562e650810bda106a9012ab20bd
https://doi.org/10.2172/714339
https://doi.org/10.2172/714339
Autor:
L.J. King, D.E. Benker, W.D. Bond, F.R. Chattin, R.G. Ross, F.G. Kitts, R.G. Stacy, J.E. Bigelow
A batch of high-burnup fuel from the Fast Flux Test Facility (FFTF) was processed in the Solvent Extraction Test Facility (SETF) during Campaign 9. The fuel had a burnup of {similar_to}0 MWd/kg and a cooling time of {similar_to} year. Two runs were m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d4b14840905e42004956d1cea200df9
https://doi.org/10.2172/712808
https://doi.org/10.2172/712808