The Experts below are selected from a list of 3954 Experts worldwide ranked by ideXlab platform
Jai K Lee - One of the best experts on this subject based on the ideXlab platform.
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requirement of Decontamination Factor for near surface disposal of proliferation resistant environmental friendly accident tolerable continual and economical reactor peacer wastes
Waste Management' 07 (WM'2007), 2007Co-Authors: Il S Kim, Ho M Ahn, Hee Y Lee, Seog Y Nam, Jai K LeeAbstract:A pyrochemical process has been introduced and utilized so that the transmutation of spent Pressurized Water Reactor(PWR) fuel in PEACER can produce mainly low and intermediate level waste for near surface disposal. Major radioactive nuclides from PEACER pyro-processing are composed of TRU and LLFP. In this study, the requirement for the final waste from PEACER is evaluated based on the methodology for establishment of waste acceptance criteria. Also, sensitivity analysis for several input parameters is conducted in order to determine acceptable Decontamination Factor (DF) and LLFP removal efficiency and to find out input parameter that extremely have an effect on DF. As a result of the study, LLFP removal efficiency, especially Sr-90 and Tc-99, is proved to be a major nuclide which contributes to annual dose by human intrusion scenario rather than TRU DF. More than 98.5% of LLFP have to be removed to meet below dose constraint within the DF more than 5.0E+03. Because of the relative short half-life of Sr-90, the increasing of the institutional control period is recommended for most important input parameter to determine DF. (authors)
T. Grangeon - One of the best experts on this subject based on the ideXlab platform.
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Improvement of a radiochemical separation for selenium 79 applications to effluents and nuclear wastes.
Talanta, 2007Co-Authors: C. Frechou, S. Aguerre, Jp. Degros, G. Kerlau, T. GrangeonAbstract:Selenium 79 is a beta emitter produced from 235U fission and is one of the long half-life radionuclides of interest in nuclear waste disposal problematic because of its potential migration capacity to the surface environment. Measurement of 79Se is particularly difficult due to its low activity in waste matrices (about 10-3 Bq g-1). A radiochemical procedure based on ion exchange separations was already described in a previous paper. This work presents different applications of the radiochemical separation to waste samples and an improvement of this procedure, including a selective extraction of selenium as diethylselenium in an organic solvent followed by a re-extraction in aqueous medium. This additional step allows the Decontamination Factor to be increased with the aim of counting 79Se by liquid scintillation counting.
Il S Kim - One of the best experts on this subject based on the ideXlab platform.
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requirement of Decontamination Factor for near surface disposal of proliferation resistant environmental friendly accident tolerable continual and economical reactor peacer wastes
Waste Management' 07 (WM'2007), 2007Co-Authors: Il S Kim, Ho M Ahn, Hee Y Lee, Seog Y Nam, Jai K LeeAbstract:A pyrochemical process has been introduced and utilized so that the transmutation of spent Pressurized Water Reactor(PWR) fuel in PEACER can produce mainly low and intermediate level waste for near surface disposal. Major radioactive nuclides from PEACER pyro-processing are composed of TRU and LLFP. In this study, the requirement for the final waste from PEACER is evaluated based on the methodology for establishment of waste acceptance criteria. Also, sensitivity analysis for several input parameters is conducted in order to determine acceptable Decontamination Factor (DF) and LLFP removal efficiency and to find out input parameter that extremely have an effect on DF. As a result of the study, LLFP removal efficiency, especially Sr-90 and Tc-99, is proved to be a major nuclide which contributes to annual dose by human intrusion scenario rather than TRU DF. More than 98.5% of LLFP have to be removed to meet below dose constraint within the DF more than 5.0E+03. Because of the relative short half-life of Sr-90, the increasing of the institutional control period is recommended for most important input parameter to determine DF. (authors)
C. Frechou - One of the best experts on this subject based on the ideXlab platform.
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Improvement of a radiochemical separation for selenium 79 applications to effluents and nuclear wastes.
Talanta, 2007Co-Authors: C. Frechou, S. Aguerre, Jp. Degros, G. Kerlau, T. GrangeonAbstract:Selenium 79 is a beta emitter produced from 235U fission and is one of the long half-life radionuclides of interest in nuclear waste disposal problematic because of its potential migration capacity to the surface environment. Measurement of 79Se is particularly difficult due to its low activity in waste matrices (about 10-3 Bq g-1). A radiochemical procedure based on ion exchange separations was already described in a previous paper. This work presents different applications of the radiochemical separation to waste samples and an improvement of this procedure, including a selective extraction of selenium as diethylselenium in an organic solvent followed by a re-extraction in aqueous medium. This additional step allows the Decontamination Factor to be increased with the aim of counting 79Se by liquid scintillation counting.
Seog Y Nam - One of the best experts on this subject based on the ideXlab platform.
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requirement of Decontamination Factor for near surface disposal of proliferation resistant environmental friendly accident tolerable continual and economical reactor peacer wastes
Waste Management' 07 (WM'2007), 2007Co-Authors: Il S Kim, Ho M Ahn, Hee Y Lee, Seog Y Nam, Jai K LeeAbstract:A pyrochemical process has been introduced and utilized so that the transmutation of spent Pressurized Water Reactor(PWR) fuel in PEACER can produce mainly low and intermediate level waste for near surface disposal. Major radioactive nuclides from PEACER pyro-processing are composed of TRU and LLFP. In this study, the requirement for the final waste from PEACER is evaluated based on the methodology for establishment of waste acceptance criteria. Also, sensitivity analysis for several input parameters is conducted in order to determine acceptable Decontamination Factor (DF) and LLFP removal efficiency and to find out input parameter that extremely have an effect on DF. As a result of the study, LLFP removal efficiency, especially Sr-90 and Tc-99, is proved to be a major nuclide which contributes to annual dose by human intrusion scenario rather than TRU DF. More than 98.5% of LLFP have to be removed to meet below dose constraint within the DF more than 5.0E+03. Because of the relative short half-life of Sr-90, the increasing of the institutional control period is recommended for most important input parameter to determine DF. (authors)
