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DETERMINATION OF THE <sup>129</sup>I IN PRIMARY COOLANT OF PWR
Choi, Ke Chon,Park, Yong Joon,Song, Kyuseok Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.1
Among the radioactive wastes generated from the nuclear power plant, a radioactive nuclide such as $^{129}I$ 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 $^{129}I$ as a representative DTM, becomes essential. In this report, the adsorption and recovery rate were measured by adding $^{125}I$ as a radio-isotopic tracer ($t_{1/2}$ = 60.14 d) to the simulation sample, in order to measure the activity concentration of $^{129}I$ 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 $^{129}I$ 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 ${\mu}g/mL$.
Sample pre-treatment for measurement of 129I in radwastes
Ke-Chon Choi,Sun-Ho Han,Kwang-Yong Jee,Ki-Seop Choi 한국방사성폐기물학회 2005 방사성폐기물학회지 Vol.3 No.1
원전에서 발생되고 있는 방사성폐기물 중 I의 정량을 위하여 시료의 특성에 맞는 최적의 시료 전처리 및 회수방법을 고찰하였다. 난용성시료 중 모의 잡고체와 수지에 함유된 요오드를 산침출법과 알칼리 용융방법으로 분리하여 회수율을 측정한 결과 , 의 회수율을 각각 나타내었다. 모의 농축폐액 중 1291를 pH 7의 음이온 수지에 흡착시켜 선택적으로 분리한 후 회수율을 측정한 결과 의 회수율을 나타내었다. 폐액 중 함유되어있는 고 농도의 붕소가 요오드 회수율에 미치는 영향을 조사한 결과 1,200 g/mL 이하의 붕소는 I의 분리 및 정량에 영향을 주지 않았다. 원전 내 현장시료인 폐수지 중 I 회수율을 칼럼용리방법으로 분리 후 측정한 결과 (RSD, )를 나타내었다. Many different kinds of radwastes are discharged from the nuclear power plants, and I is included in these radwastes. Recovery test of I was evaluated for different radwastes(dry active waste, sludge, spent resin and simulated evaporator bottom). Recovery of I for dry active waste by acid leaching with NaClO was and l291 for spent rein by alkali fusion method with KOH as a flux agent was ), respectively. iodide in simulated evaporator bottom containing a high concentration of borate was adsorbed with anion exchange resin at pH 7 phosphate buffer solution. Recovery of I for anion exchange resin was and not affected up to 1,200 g/mL (as a Boron). Recovery of I for the spent resin from nuclear power plant was .
Park, Yong Joon,Choi, Ke-Chon,Ha, Yeong-Keong Korean Nuclear Society 2016 Nuclear Engineering and Technology Vol.48 No.2
The solubility of nickel ferrite in an aqueous solution of boric acid was studied by varying the pH at the temperatures ranging from $25^{\circ}C$ to $320^{\circ}C$. A flow-through autoclave system was specially designed and fabricated to measure the solubility of Fe in hydrothermal solutions under high temperature and pressure. The performance of this flow-through system was directly compared with the conventional static state technique using a batch-type autoclave system. The stability of fluid velocity for the flow-through autoclave system was verified prior to the solubility measurement. The influence of chemical additives, such as boric acid and $H_2$, on the solubility of nickel ferrite was also evaluated.