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이민수,백승우,김광락,안도희,임성팔,정홍석,최희주,최종원,손순환,송규민,Lee, Min-Soo,Paek, Seung-Woo,Kim, Kwang-Rag,Ahn, Do-Hee,Yim, Sung-Paal,Chung, Hong-Suk,Choi, Heui-Joo,Choi, Jeong-Won,Son, Soon-Hwan,Song, Kyu-Min 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.2
월성 원자력 발전소의 TRF 시설에서 수집된 트리튬을 metal hydride 형태로 보관하고 있는 500 kCi급 트리튬 1차 저장용기를 발전소 밖의 폐기물 저장고로 안전하게 운반하기 위하여 트리튬 운반용기를 개발하였다. B형 운반용기의 기술기준을 적용하여 구조평가, 열평가, 방사선차폐평가, 격납평가 등을 수행하여 운반용기의 안전성을 분석하였다. 트리튬 운반용기는 정상운반조건 및 사고운반조건에서도 격납 경계가 손상되지 않는다고 평가되었다. 붕괴열로 인한 운반용기 내부 저장용기의 온도상승은 수치해석 결과, 원통형 모델에서는 $134.8^{\circ}C$로 나타났다. 운반사고 조건에 대한 열 평가로서 $800^{\circ}C$ 외부환경에 30분간 노출되었을 경우에는 단열재만의 열차폐를 고려하여 계산한 결과, 약 $405^{\circ}C$로 나타났으며, 내부 온도 상승은 1차 격납 경계인 1차 저장용기의 허용 온도인 $550^{\circ}C$에도 미치지 못하였다. 격납 차폐 평가에서도 사고조건인 $800^{\circ}C$의 외부 환경에 노출된 경우에서도 충분히 운반용기의 격납 성능을 유지할 수 있다고 판단되었다. 방사선에 대한 차폐 특성을 조사한 결과, 트리튬에서 발생된 ${\beta}-ray$ 선량은 1차 저장용기 외부 표면에서 0으로 계산되었다. 이상과 같이 500 kCi 급 트리튬 운반용기에 대한 안전성을 평가한 결과, 운반사고조건에서도 트리튬 운반용기는 전혀 이상이 없는 것으로 나타났다.
포스터 발표 - 무기재료분과 / 전기화학분과 / 촉매분과 : 비활성 알루미나 충전컬럼에서의 수소동위원소 분리특성
김광락,강희석,백승우,이성호,안도희,이한수,정흥석 ( Kwang Rag Kim,Hee Suk Kang,Seung Woo Paek,Sung Ho Lee,Do Hee Ahn,Han Soo Lee,Hong suk Chung ) 한국공업화학회 1997 한국공업화학회 연구논문 초록집 Vol.1990 No.3
N/A In the fields of operation and handling of the hydrogen isotope facility, and of management technology for the nuclear fusion source, gas chromatography has been used as one of the practical techniques for the separation and the enrichment of hydrogen isotopic gases including tritium. Chromatographic separation experiments of the hydrogen isotope mixture (hydrogen, deuterium and tritium) were carried out by use of a commercially available gas chromatograph. An aliquot of the gas sample was injected with a specially designed vacuum sampler into the stream of inert carrier gas which goes through the separation column at liquid nitrogen temperature. The complete separation of hydrogen isotopic molecules was observed with an alumina adsorbent partially deactivated by coating with 10% manganese chloride. In addition, fairly good separation conditions without appearance of the nuclear spin isomers in a shorter retention time, which would be useful for the practical applications of the hydrogen isotope separation and enrichment, were obtained.
김광락,강희석,백승우,이성호,안도희,이한수,정흥석 ( Kwang Rag Kim,Hee Suk Kang,Seung Woo Paek,Sung Ho Lee,Do Hee Ahn,Han Soo Lee,Hong suk Chung ) 한국공업화학회 1997 한국공업화학회 연구논문 초록집 Vol.1997 No.0
N/A In the fields of operation and handling of the hydrogen isotope facility, and of management technology for the nuclear fusion source, gas chromatography has been used as one of the practical techniques for the separation and the enrichment of hydrogen isotopic gases including tritium. Chromatographic separation experiments of the hydrogen isotope mixture (hydrogen, deuterium and tritium) were carried out by use of a commercially available gas chromatograph. An aliquot of the gas sample was injected with a specially designed vacuum sampler into the stream of inert carrier gas which goes through the separation column at liquid nitrogen temperature. The complete separation of hydrogen isotopic molecules was observed with an alumina adsorbent partially deactivated by coating with 10% manganese chloride. In addition, fairly good separation conditions without appearance of the nuclear spin isomers in a shorter retention time, which would be useful for the practical applications of the hydrogen isotope separation and enrichment, were obtained.
액체음극에서의 금속 수지상 성장 억제를 위한 교반기 성능평가
김시형,윤달성,유영재,백승우,심준보,안도희,Kim, Si-Hyung,Yoon, Dal-Seong,You, Young-Jae,Paek, Seung-Woo,Shim, Joon-Bo,Ahn, Do-Hee 한국방사성폐기물학회 2009 방사성폐기물학회지 Vol.7 No.2
An electrolytic system (zinc anode-gallium cathode) was setup to evaluate the performance of several stirrers prepared for this study, where stirrers have been used to prevent uranium from forming dendrite on the cathode in pyrochemical process. In the case of no-stirring condition, zinc dendrites began to grow on the gallium surface in 1 hour and some dendrite grew out of the cathode crucible around 6 hours. When a rectangular stirrer or a tilt stirrer was rotated, at 40${\sim}$150 rpm, to mix the liquid gallium cathode, dendritic growth of zinc metal was prevented irrespective of revolution speed, but some of the deposits overflowed out of the cathode crucible owing to the large centrifugal forces at 150 rpm. The harrow stirrer did not nearly retard the dendrite growth at 40 rpm, but the dendrite growth was retarded at higher than 100 rpm and the zinc deposits also did not overflow at 150 rpm. Pounder could also prevent the dendrite growth to some extent but it had some difficulties in operation compared with other types of stirrers.