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가압경수로형 원전에서 발생된 폐수지의 $^{14}C$ 및 $^3H$ 동시 분리 및 측정
박순달,김정석,김종구,한선호,지광용,Park, Soon-Dal,Kim, Jung-Suck,Kim, Jong-Goo,Han, Sun-Ho,Jee, Kwang-Yong 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.3
In this work $^{14}C\;and\;^3H$ distribution characteristics of spent resins from nuclear power plants(NPPs), pressurized water reactors(PWRs), was investigated. It was found that the recovery percent of $^{14}C$ by the wet oxidation-acid stripping was $81%{\sim}100%$ for the added activity range of $^{14}C,\;0.72\;Bq{\sim}460\;Bq$, and it was not affected by the kinds of stripping acids, 3N-HCl, $3\;N-HNO_3\;and\;3\;N-H_2SO_4$. And the recovery percent of $^3H$ by distillation using the same apparatus was $81%{\sim}101%$ for the added activity range of $^3H,\;0.60\;Bq{\sim}435\;Bq$. Among the tested stripping acids, 3\;N-HCl, $3\;N-HNO_3\;and\;3\;N-H_2SO_4$, only the trapped $^3H$ solution by distillation in $3\;N-H_2SO_4$ was compatible with the 3H scintillator, Ultimagold XR. Neither of the $^{14}C\;and\;^3H$ trapping solutions from the spent ion exchange resin samples by the wet oxidation-3 $N-H_2SO_4$ stripping contained gamma nuclides. However, some gamma nuclides, $^{60}Co,\;^{134}Cs,\;^{137}Cs\;and\;^{54}Mn$, were found in the trapped $^3H$ solutions of the spent resins by the wet oxidation-3 N-HCl stripping. It was the same for the $^3H$ trapping solutions of the spent resins by Sample Oxidizer(PACKARD MODEL 307). Meanwhile only two nuclides, $^{134}Cs,\;and\;^{134}Cs$, were found in the $^{14}C$ trapping solutions of the spent resins by Sample Oxidizer(PACKARD MODEL 307). It was found that most of the $^{14}C$ in the spent resins existed as inorganic carbon form, more than about 70% of the total $^{14}C$ content. Among the analyzed 30 spent ion exchange resin samples, the average concentration of $^{14}C$ and $^3C$ for the high radioactive samples, 8 samples, was $19000\;Bq/g{\pm}41000\;Bq/g,\;670\;Bq/g{\pm}460\;Bq/g$ and that for the low radioactive samples, 22 samples, was $4.2\;Bq/g{\pm}4.3\;Bq/g,\;6.0\;Bq/g{\pm}5.3\;Bq/g$, respectively. And the average $^{14}C/^3H$ ratio for the high radioactive samples, was higher, 28, than that of low radioactive samples, 0.70. Some linear relationship trend was found between the activity concentrations of $^{14}C\;and\;^3H$.
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알파분광분석법에 의한 $^{237}Np$ 정량 및 사용후핵연료 시료에의 적용
조기수,김정석,한선호,박영재,김원호,Joe Kih-Soo,Kim Jung-Suck,Han Sun-Ho,Park Yeong-Jai,Kim Won-Ho 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.2
Alpha spectrometry was studied for the determination of $^{237}Np$ in spent nuclear fuel samples. The optimum condition for the electrodeposition of $^{237}Np$ was obtained as follows : for $1{\sim}1.5$ hour of deposition time, at the current intensity of $1.2{\sim}1.5$ A and at sodium sulfate electrolyte without organic additive. The deposition yield and its reproducibility on $^{237}Np$ was decreased as the amount of $^{237}Np$ decreased from 4.16 Bq down to 0.0264 Bq(1ng). The recovery yield of $^{237}Np$ determined by alpha spectrometry after separation in synthetic solution was $98.8{\pm}5.1%$(n=4). The contents of $^{237}Np$ in spent nuclear fuel samples were determined and the result showed an agreement within 10% of a difference between the measurement and the calculation.
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환경성을 고려한 폐 복합재료(CFRP)의 재활용기법에 대한 연구
이철규(Lee Cheul-Kyu),김용기(Kim Yong-Ki),피라다(Pruitichaiwiboon-Phirada),김정석(Kim jung-Suck),주창식(Ju Chang-Sik) 한국철도학회 2008 한국철도학회 학술발표대회논문집 Vol.- No.-
Various efforts of reducing the green house gas in the whole industrial fields including railway industry have been implemented. Tilting train is the key example because it can run more faster on the existing rail than others due to its composite body. The system has an advantage of light weight but also a task to solve, recycling of composite material. To recycle the CFRP(Carbon Fiber Reinforced Plastic), there are two typical methods; chemical and thermal method. In this study, more environmentally friendly recycling method was recommended through the environmental function through comparing both recycling methods.
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한글 처리를 위한 文字多重防送 시스템의 說計에 관한 硏究
金正錫,金容得 亞洲大學校 1986 論文集 Vol.9 No.-
In this paper, we studied the design of the Teletext system which was used for the process of the Hangul in Korean broadcasting system. At present Teletext system, the Hangul has been processed using DRCS, but in this study we used the Hangul synthesis program for the saving of the TV display time of data and the memory size.
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