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전관식,박현수,이건재,김병태,이후근 한국화학공학회 1987 Korean Chemical Engineering Research(HWAHAK KONGHA Vol.25 No.2
다공판탑에서 물에 의한 질소산화물의 흡수결과 생성되는 액상의 HNO₃와 HNO₂의 ��도를 측정·분석하였다. NO_x 흡수가 기상의 N₂O₄ 농도에 지배된다고 가정한 제1보와는 달리 기상의 N₂O₄뿐 아니라 N₂O₃의 농도가 NO_x 흡수를 지배한다고 가정하여 전개한 흡수모델로 부터 얻은 이론값과 실험치를 비교한 결과 비교적 잘 일치하는 경향을 나타내었으며, HNO₂는 농도가 높을수록 급격히 분해하는 경향을 나타내었다. The cuncentratiuns uf HNO₃ and HNO₂ in liquid phase produced from the absorption of NO_x into water in a sieve tray column were measured and analyzed. The mathematical model in the Part Il of this study was developed in the assumption that the absorption of NO_x would be governed by the concentration of gaseous N₂O₃ as well as the concentration of gaseous N₂O₄, but in the Part l, the concentration of gaseous N₂O₄ had been considered as the only active parameter in the absorption process of NO_x. With the comparison between the theoretical values from this mathematical model and experimentals, they were in good agreement and HNO₂ tended to be dissociated rapidly at the higher concentration of HNO₂.
전관식,유성현,조영준,홍장표,한욱진,최병순,강필상,조석주,Chun, Kwan-Sik,Yoo, Sung-Hyun,Cho, Young-June,Hong, Jang-Pyo,Han, Wook-Jin,Choi, Beong-Soon,Kang, Pil-Sang,Cho, Suk-Ju 한국방사성폐기물학회 2009 방사성폐기물학회지 Vol.7 No.3
To evaluate the efficiency of the decontamination plant for the removal of uranium compounds deposited on the internal surface of $UF_6$ cylinder for its reuse, two demonstration tests of the plant with different ratio of ${Na_2}{CO_3}$ and ${H_2}{O_2}$ were carried out, and each test had 5 steps. The main chemical form removed by the tests was to be identified as ${Na_4}{UO_2}(CO_3)_3$. More than 50% of uranium was removed by water of the first step, and at the following steps the removal amounts were exponentially decreased. On the other hand, the result shows that the injected amount of ${Na_2}{CO_3}$, compared with that of the removed uranium, was stoichiometrically excessed. This suggests that the injected amounts of ${Na_2}{CO_3}$, the generation rate of decontaminated waste, and the decontamination steps could be reduced by a process optimization of the plant.
Effect of engineered barriers on the leach rate of cesium from spent PWR fuel
전관식,김승수,최종원,Chun Kwan Sik,Kim Seung-Soo,Choi Jong-Won Korean Radioactive Waste Society 2005 방사성폐기물학회지 Vol.3 No.4
To identify the effect of engineered barriers on the leach rate of cesium from spent PWR fuel under a synthetic granitic groundwater, the related leach tests with and without bentonite or metals have been performed up to about 6 years. The leach rates were decreased as a function of leaching time and then became a constant after a certain period. The period in a bare spent fuel was much longer than that with bentonite or metal sheets. The cumulative fraction of cesium released from the spent fuel with bentonite or with copper and stainless steel sheets was steadily increased, but the fraction from bare fuel was rapidly and then sluggishly increased. However, the values deducted its gap inventory from the cumulative fraction of cesium released from the bare fuel was almost very close to the others. These suggest that the initial release of cesium from bare fuel might be dependant on its gap inventory and the effect of engineered barriers on the long-term leach rate of cesium would be insignificant but the rate with engineered barriers could be reduced in the initial transient period due to their retardation effect. And the long-term leach rate of cesium from spent fuel in a repository would be approached to a constant rate of $2\times10^{-2}g/m^2-day$.
처분환경조건에서 모의 방사성폐기물 붕규산유리고화체의 장기침출률
전관식,김승수,최종원 한국방사성폐기물학회 2003 방사성폐기물학회지 Vol.1 No.1
심부 처분환경조건에서 붕규산유리고화체의 장기침출거동을 규명하기 위하여 3종의 모의붕규산유리고화체에 대한 장기침출실험이 1997년에 착수되었다. 5년간의 침출결과는 붕소가 본 붕규산유리고화체의 장기침출지표물질로 사용될 수 있음을 확인시켜 주었고, 비록 고화체들의 조성은 약간씩 다르지만, 초기 1년여 기간동안의 침출률을 제외한 장기침출률은 S/V에도 무관하게 0.03g/$m^2$-day 에 근접하는 경향을 보여주고 있다. To understand the long-term leach behavior of a borosilicate Waste glass in a repository, the leaching experiment with three kinds of simulated borosilicate waste glasses has been carried out since the middle of 1997. The five years results indicate that a boron would be applied as an indicator of a long-term leaching of their borosilicate waste glasses and that their long-term leach rates have a tendency to be close to about 0.03g/$m^2$-day even though their compositions and their ratios of the surface area to the volume of leachate are different.