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Determination of ^(129)I in simulated radioactive wastes using distillation technique
최계천,송병철,한선호,박용준,송규석 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.3
It is clarified in the radioactive waste transfer regulation that the concentration of radioactive waste for the major radio nuclide has to be examined when radioactive waste is guided to the radioactive waste stores. In case of the low level radioactive waste sample, the analytical results of radioactive waste concentration frequently show a value lower than minimum detectable activity (MDA). Since the MDA value basically depends on the amount of a sample,background value, measurement time, counting efficiency, and etc, it would be necessary to increase a sample amount with a intention of minimizing MDA. In order to measure a concentration of ^(129)I in low and medium level radioactive waste, ^(129)I was collected by using a distillation technique after leaching the simulated radioactive waste sample with a non-volatile acid. The recovery of 129I measured was compared with that measured with column elution technique which is a conventional method using an anion-exchange resin. The recovery of inactive iodide by using the distillation method and column elution were found as 86.5 0.9% and 87.3 2.7%, respectively. The recovery and MDA value calculated for distillation technique when 100 g of extracted solution of ^(129)I was taken,were found to be 84.6 1.6% and 1.2 10-4 Bq/g, respectively. Consequently, the proposed technique with simplified process lowered the MDA value more than 10 times compared to the column elution technique that has a disadvantage of limited sampling amount. 방사성폐기물이 처분장에 인도 될 때 주요 방사성 핵종의 방사능 농도를 규명 하도록 방사성폐기물 인도 규정에 명시되어 있다. 저준위 방사성폐기물 시료의 경우 측정된 방사능 농도가 최소검출 방사능 농도(MDA: Minimum dectable activity) 이하의 값을 나타낼 경우가 많으며, MDA는 시료의 양, 바탕 값, 계측시간 및 계측효율 등에 따라서 달라지므로 MDA를 낮추기 위하여 가능한 많은 양의 시료를 취할 필요가 있다. 모의 잡고체 시료에 첨가된 요오드의 회수율을 결정하기 위한 방법으로서 모의 시료 중 비 방사성 요오드를 비휘발성 산으로 침출시킨 후 침출액을 직접 증발시키는 방법과 음이온 교환수지를 이용하여 I-를 흡착하여 분리하는 칼럼용리방법으로 측정하여 회수율을 비교한 결과, 증류법과 칼럼용리방법의회수율은 각각 86.5±0.9%, 87.3±2.7%로 나타났다. 증류법에 의한 모의 방사성 시료 중 ^(129)I 요오드의회수율 및 MDA는 84.6±1.6%, 1.2×10-4 Bq/g로 각각 나타났으며, 분리공정을 단순화하고 많은 양의 시료를 취함으로써, 칼럼용리 방법의 단점을 보완하고 10배 이상 MDA를 낮출 수 있는 결과를 얻을 수 있었다.
증류법을 이용한 모의 방사성폐기물 중 <sup>129</sup>I 의 정량
최계천,송병철,한선호,박용준,송규석,Choi, Ke-Chon,Song, Byung-Cheol,Han, Sun-Ho,Park, Yong-Joon,Song, Kyu-Seok 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.3
방사성폐기물이 처분장에 인도 될 때 주요 방사성 핵종의 방사능 농도를 규명 하도록 방사성폐기물 인도 규정에 명시되어 있다. 저준위 방사성폐기물 시료의 경우 측정된 방사능 농도가 최소검출 방사능 농도(MDA: Minimum dectable activity) 이하의 값을 나타낼 경우가 많으며, MDA는 시료의 양, 바탕 값, 계측시간 및 계측효율 등에 따라서 달라지므로 MDA를 낮추기 위하여 가능한 많은 양의 시료를 취할 필요가 있다. 모의 잡고체 시료에 첨가된 요오드의 회수율을 결정하기 위한 방법으로서 모의 시료 중 비 방사성 요오드를 비휘발성 산으로 침출시킨 후 침출액을 직접 증발시키는 방법과 음이온 교환수지를 이용하I-를 흡착하여 분리하는 칼럼용리방법으로 측정하여 회수율을 비교한 결과, 증류법과 칼럼용리방법의 회수율은 각각 $86.5{\pm}0.9%$, $87.3{\pm}2.7%$로 나타났다. 증류법에 의한 모의 방사성 시료 중 $^{129}I$ 요오드의 회수율 및 MDA는 $84.6{\pm}1.6%$, $1.2{\times}10^{-4}Bq/g$로 각각 나타났으며, 분리공정을 단순화하고 많은 양의 시료를 취함으로써, 칼럼용리 방법의 단점을 보완하고 10배 이상 MDA를 낮출 수 있는 결과를 얻을 수 있었다. It is clarified in the radioactive waste transfer regulation that the concentration of radioactive waste for the major radio nuclide has to be examined when radioactive waste is guided to the radioactive waste stores. In case of the low level radioactive waste sample, the analytical results of radioactive waste concentration frequently show a value lower than minimum detectable activity (MDA). Since the MDA value basically depends on the amount of a sample, background value, measurement time, counting efficiency, and etc, it would be necessary to increase a sample amount with a intention of minimizing MDA. In order to measure a concentration of $^{129}I$ in low and medium level radioactive waste, $^{129}I$ was collected by using a distillation technique after leaching the simulated radioactive waste sample with a non-volatile acid. The recovery of $^{129}I$ measured was compared with that measured with column elution technique which is a conventional method using an anion-exchange resin. The recovery of inactive iodide by using the distillation method and column elution were found as $86.5{\pm}0.9%$ and $87.3{\pm}2.7%$, respectively. The recovery and MDA value calculated for distillation technique when 100 g of extracted solution of $^{129}I$ was taken, were found to be $84.6{\pm}1.6%$ and $1.2{\times}10^{-4}Bq/g$, respectively. Consequently, the proposed technique with simplified process lowered the MDA value more than 10 times compared to the column elution technique that has a disadvantage of limited sampling amount.
Determination of the 129I in Primary Coolant of PWR
최계천,박용준,송규석 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.1
Among the radioactive wastes generated from the nuclear power plant, a radioactive nuclide such as 129I is classified as a difficult-to-measure (DTM) nuclide, owing to its low specific activity. Therefore, the establishment of an analytical procedure,including a chemical separation for 129I as a representative DTM, becomes essential. In this report, the adsorption and recovery rate were measured by adding 125I as a radio-isotopic tracer (t1/2 = 60.14 d) to the simulation sample, in order to measure the activity concentration of 129I in a pressurized-water reactor primary coolant. The optimum condition for the maximum recovery yield of iodine on the anion exchange resins (AG1 x2, 50-100 mesh, Cl- form)was found to be at pH 7. In this report, the effect of the boron content in a pressurized-water reactor primary coolant on the separation process of 129I was examined, as was the effect of 3H on the measurement of the activity of iodine. As a result, no influence of the boron content and of the simultaneous 3H presence was found with activity concentrations of 3H lower than 50 Bq/mL, and with a boron concentration of less than 2,000 μg/mL.