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이민수,정홍석,임성팔,안도희,김광락,이성호,백승우,민병윤 한국공업화학회 2003 응용화학 Vol.7 No.2
In this paper, the foaming method of polymer concrete was studied. The pre-composition of polymer concrete consisted of unsaturated polyester as a binder material 15∼50wt%, sand 0∼80 wt%, filler 5-50 wt%, and foaming agent 0.1∼1.5 wt%. The pre-composition was heated at 100∼200℃ for 30∼120 minutes, which thermal treatment caused hardening of unsaturated polyester and cracking of foaming agent. The foamed polymer concrete showed low thermal transfer coefficent together with good mechanical properties.
이민수,정홍석,임성팔,안도희,김광락,이성호,백승우,정해성,조연구 한국공업화학회 2003 응용화학 Vol.7 No.1
In this paper, the composition of lead glass was studied to lower the melting temperature. The composition of lead glass was silica, lead monoxide, sodium hydroxide, and other metal oxides which were blended in alkaline aqueous solution. The blend was dried and melted to produce transparent glass material. Using the composition suggested in this paper, it was possible to manufacture transparent lead glass easily at 700~900 ℃. And the dried bled material had very low softening temperature around 200℃ which can be applied in inorganic adhesives.
김광락,이민수,백승우,이성호,안도희,임성팔,정홍석 한국공업화학회 2003 응용화학 Vol.7 No.1
The immobilized hydrogen a titanium hydride could be used In a stainless steel vessel for the long-term storage of hydrogen isotopes. In order to predict the safety concerns of storage vessel at elevate temperature, a comprehensive mathematical model has been developed for diffusion analysis of hydrogen isotopes in the stainless steel vessel. Numerical results showed that significant amount of hydrogen isotopes could be released by permeation through the vesscl wall of 7mm thick at the 800℃ of hypothetical fire accident condition. A rapid permeation of tritium gives steady state permeation is achieved in approximately 5 hours at this temperaturc.
김광락,이민수,백승우,이성호,안도희,임성팔,정흥석 한국공업화학회 2003 응용화학 Vol.7 No.2
The immobilized hydrogen as a titanium hydride could be used in a stainless steel vessel for the long-term storage of hydrogen isotopes. The design analysis of a hydrogen isotope transport container with capacity of 0.5 MCi tritium was carried out to confirm the performance of the safely requirement. In order to verify that the radioactive transport container complies with the requirements for the B(U) type container stipulated in the MOST regulation of transport container, thermal analysis were made for normal condition and hypothetical accident conditions during transport. Thermal analysis with the Heating-7 code under conditions of 38℃ for 7 days and 800℃ for 30 minutes showed that the container complied with the requirement for B(U) type transport container.
김광락,백승우,이민수,이성호,안도희,임성팔,정홍석 한국공업화학회 2002 응용화학 Vol.6 No.2
In the hydrogen isotope facility and the fiel cycle of the fision reactor, an effective means for analyzing hydrogen isotopes and decay product(helium) of tritium is very importat from the viewpoint of system operation and control. Chromatographic separation of the hydrogen isotopes mixture from titanium hydride was carried out by gas chromatograph at-196℃ for quantitative analytical purpose.Neon and partially deactivated alumina were employed as the carrier gas and the fixed column, respectively. The chromatogram with complete separation was observed in order ofH_2, HD and D_2 by the thermal conductivity detector. In addition, fairly good separation conditions were obtained in a shorter retention time without any appearance of nuclear spin isomers for the practical applications of the hydrogen isotope separation and analysis.
수소동위원소 저장을 위한 티타늄 스폰지 금속의 활성화 특성
백승우,안도희,김광락,임성팔,이성호,이민수,정홍석 한국공업화학회 2003 응용화학 Vol.7 No.2
Titanium sponge has been selected as a suitable material for tritium immobilization. The purpose of this paper describes the experimental data which supplies the imformation for the activation process of the titanium sponge for the storage of tritium. The influences of the different variables, such as activation temperature, time, and pressure, on the hydriding properties of the titanium sponge were investigated. From the experimental results, it was found that 400℃ was the minimum activation temperature of the titanium sponge gor the hydriding reaction. However, 500℃ was selected as the activation temperature of the titanium sponge and the activation procedure, which is now being used for other experiments, which is heating for two hours at 500℃ while maintaining a minimum cacuum of 1.0x10 EXP (6) torr.
백승우,안도희,김광락,임성팔,이성호,이민수,정홍석 한국공업화학회 2002 응용화학 Vol.6 No.2
A TRF(Tritium Removal Facility) will be constructed at Wolsong Plant to remove thetritium from heavy water. This facility will reduce operator exposure and tritiumemissions from operating reactors. The recovered tritium must be safely packaged forlong-term storage. Packaging tritium as a solid metal tritide is preferred over gaseoustritium due to the concem for gas leakage. Titanium sponge has been selected assuitable material for tritium product immobilization. This study describes theinformation on practical use of prototype tritium storage vessel. Experimental works were conducted to determine procedures for preparation of titanium tritides and to evaluate capacity of titanium sponge in tritium storage.
백승우,안도희,김광락,임성팔,이성호,이민수,정홍석 한국공업화학회 2003 응용화학 Vol.7 No.1
A TRF(Tritium Removal Fcaility) will be constructed at Wolsong Plant to remove the tritium from heavy water. Titanium sponge tas been selected as suitable material for tritium product immobilization. This study between titanium sponge and hydrogen isotopes. The activation temperature required for hydriding of titanium was determined 500˚C The hydriding reaction between hydrogen and titanium was very fast with rapid increasing of temperature and reached to the saturated state within 10 minutes. There was no significant isotopic effect in the reaction of hydrogen and deuterium and the hydriding rates were prevented by helium content in reacting hydrogen gas.
심명화,정홍석,김창석,백승우,안도희,이민수,김광락,임성팔 한국공업화학회 2005 응용화학 Vol.9 No.1
The main purpose of fusion fuel supply system is to store and supply hydrogen isotopes needed for operation of ITER and to provide the necessary infrastructure for short and long term storage of large amount of hydrogen isotopes. The storage of tritium as metal tritide on hydride forming metals or intermetallic compounds is recognized as the most reliable and safe method. Considering the advantages and disadvantages of several hydrogen isotope getter materials, the authors suggest the use of ZrCo on the basis of its ideal P-T-C characteristics and its non pyrophoricity. The authors also suggest the hydrogen isotope storage beds design appropriate to the fusion fuel supply system.