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김연두,장원표,유석상 忠南大學校 1971 論文集 Vol.10 No.-
This experiment was conducted to find out uranium in graphites occurring in Ockchun boundary in Korea. About 200㎞, from Junjoo to Wonjoo, belongs to graphite of Ockchun boundary, we have investigated out resources of uranium, vanadium and molybdenum. The separation of uranium vanadium and molybdenum was carried out with a liquid anion exchanger such as Amberlite LA-1 and Amberlite LA-2 diluted with Xylene. These elements separated in the above method were quantitatively analyzed by colorimetric method after developing with H_2O_2, NaCNS and H_2O_2 in every solution. It was found that the highest contents of uranium was 0.2 percent in the samples of Taejon Geosan, and Keumsan.
국산 흑연 용도 개발에 관한 연구 : 제1보, 흑연정제에 관한 연구 Part 1. Refining of Natural Graphite
김진선,장원표 忠南大學校 1974 論文集 Vol.13 No.1
As a part of studies on the utilization of natural graphite, which is farily abundant in Korea, a refining method of graphite has been investigated. Among several feasible methods, alkali leaching method was adopted for this purpose. Flaky graphite which usually contains mica, sand and clay as impurities was soaked in or moistened with caustic soda solution and heated in an autoclave or in a bomb to about 400℃ to react with acid insoluble materilas. The reacted material was leached with water to wash off the alkali soluble matter and the excess caustic alkali. The residue was leached with dilute acid to remove insoluble metal oxides and silicates. Throughout the test, several examinations were made to obtain optimum conditions such as concentration of caustic soda, reaction temptrature, reaction time, acid concentration, etc. It was found that multiple leaching and flotation after each leaching was very effective to decrease impurities. At an optimum condition, the impurity of 19% was decreased to 1% after the first leaching, to 0.1% after the 2nd leaching and to 0.02% after the 3rd leaching.
김연두,장원표,유석상 忠南大學校 1971 論文集 Vol.10 No.-
A new separation method of minor amounts of uranium was applied to the determination of uranium contents in monazites occurring in Kongju and Choongju in Korea. The separation method with a liquid anion exchanger such a Amberlite LA-2 diluted with xylene was faster and simpler than that with a solid exchanger resin. The samples of monazite were dissolved in hot and concentrated H_2SO_4. In 10N HCl, Uranium was quantitatively extracted by the organic phase, The stripping of uranium from the organic phase was carried out with 0.3N HNO_3. After reduction of iron, vanadium and molybdenum with H_2SO_3, the complete separation of uranium was possible by the extraction with the organic phase in 0.5N H_2SO_4. Uranium thus separated was determined colorimetrically after the development with H_2O_2. It was found that the cations such as C_e(Ⅲ), T_h(Ⅳ), V(Ⅴ), Z_n(Ⅱ), M_o(Ⅵ), C_u(Ⅱ), T_i(Ⅳ), M_n(Ⅱ) and F_e(Ⅲ), did not make any errors in the procedure (Table 3). Anions such as sulfate. phosphate, carbonate and chloride did not interfere on the separation of uranium (Table 4). The results of the analysis of monazite and graphite were showed at Table 5.
高分子量 Amine에 의한 亞鉛의 抽出分離에 關한 硏究
金天漢,朴文奎,張元杓 忠南大學校 1971 論文集 Vol.10 No.-
Zn^2+ is extracted with high molecular highly branched amme such as Amberlite LA-1 diluted with xylene from aqueous phase of 20 V% H_2SO_4-2MHCI system. Several other elements, especially Fe^3+ and Cu^2+ which are commonly associated with zinc in ore, are co-extracted. As Practical application of above extraction for the determination of zinc in ore, a prior reduction of Fe^3+ to Fe^2+ and Cu^2+ to Cu^0 with Pb-amalgam was studied. This has substantially improved the removal of Fe^3+, large amount of which will make impossible to clear separation of Zn^2+ thereafter, and Cu,^2+ which causes indicator blocking in ELTA titration even after the masking with cyanide. Thus the determination of small amount of zinc even in pyrite or chalcopyrite was possible.
Web WorkFlow를 이용한 연구개발 공정 및 연구결과물 의사결정지원시스템
정관성,이용범,장원표,한도희 한국경영과학회 2002 한국경영과학회 학술대회논문집 Vol.- No.1(1)
원자력 중장기 연구개발 일환으로 수행중인 "액체금속로 설계기술개발" 프로젝트는 개념 설계분야와 기반기술구축 분야로 구성되어 있는 상호 긴밀한 연계가 강조되는 프로젝트이다. 대과제를 중심으로 각 세부과제 및 분야 내에서 시스템별 인터페이스 등이 종합적으로 관리되어야 할 필요성이 있는 프로젝트이다. "액체금속로 설계기술개발" 프로젝트의 연구생산성 향상을 위해 공정계획을 수립하고, 프로젝트 수행 중에 산출되는 연구결과물을 검증하여 검증된 자료를 프로젝트 수행원들에게 공유할 수 있게 Web WorkFlow를 이용한 자료 검증/공유시스템을 개발하여 운영하고 있으며, 최종적으로 검증된 자료는 데이터베이스를 구축하여 활용하고 있다. 이렇게 함으로써 한국원자력연구소에서 개발중인 "액체금속로 설계 기술개발" 프로젝트를 최적화된 계획 및 관리를 통하여 연구개발을 수행할 수 있을 것으로 예상된다.
입자 크기별 가공부산물로 제조된 벌크흑연의 기계적 성질
이상혜,이상민,장원표,노재승 한국분말야금학회 2021 한국분말재료학회지 (KPMI) Vol.28 No.1
Bulk graphite is manufactured using graphite scrap as the filler and phenolic resin as the binder. Graphite scrap, which is the by-product of processing the final graphite product, is pulverized and sieved by particle size. The relationship between the density and porosity is analyzed by measuring the mechanical properties of bulk graphite. The filler materials are sieved into mean particle sizes of 10.62, 23.38, 54.09, 84.29, and 126.64 μm. The bulk graphite density using the filler powder with a particle size of 54.09 μm is 1.38 g/cm3, which is the highest value in this study. The compressive strength tends to increase as the bulk graphite density increases. The highest compressive strength of 43.14 MPa is achieved with the 54.09 μm powder. The highest flexural strength of 23.08 MPa is achieved using the 10.62 μm powder, having the smallest average particle size. The compressive strength is affected by the density of bulk graphite, and the flexural strength is affected by the filler particle size of bulk graphite.