• Resources Recycling
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• v.23 no.1
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• pp.25-32
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• 2014

The purpose of this research is to develop a process and a system to collect, purify and reuse the residual quantity of trimethylgallium, used as a raw material, upon GaN epitaxial growth for LED from a metal organic chemical vapor deposition(MOCVD) equipment. This research reviews whether TMGa collected from the process can be used through a chemical and structural characteristics evaluation. As a result of analyzing the purity using ICP-MS and ICP-AES, 7N high purity (99.99999%) of TMGa was obtained. According to checking the structural change of TMGa through NMR analysis, TMGa having pure $(CH_3)_3Ga$ structure was obtained without structural change. For reliability review of the collected TMGa, u-GaN was deposited using the MOCVD process and an structural, optical and electrical characteristics evaluation was conducted. As a result, it was found out that the reuse was possible.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.3
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• pp.167-174
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• 2009

A comprehensive analysis has been conducted on the purity of the uranium product generated from a pyroprocessing of EBR-II spent fuel. The analysis results were compared to the low-level waste criteria for both ROK and USA under a collaborative program between INL and KAERI. It is found that the US LLW definition does not include the activity from any U isotopes, but the Korean one does. The analysis results show that Pu-239 is the only alpha emitting isotope other than U isotopes that exceed the limit in the EBR-II U product. Pu contamination of the product seems to be drastically reduced in a preliminary test of the modified cathode process, and the further development of the proposed technology may be possible to meet the US LLW criteria.

• Applied Chemistry for Engineering
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• v.30 no.5
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• pp.591-596
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• 2019

A recently developed propellant, ammonium dinitramide (ADN, $NH_4N(NO_2)_2$ is stable and safe at an ambient condition. However, it requires high purity for practical applications. A very little quantity of foreign impurities in ADN may cause clogging of thruster nozzles and catalyst poisoning for the use of a liquid propellant. Thus, several purification processes for precipitated ADN particles such as repetition extraction, activated carbon adsorption and low-temperature extraction were presented in this study. The purifying methods helped to improve the chemical purity as evaluated by FT-IR and UV-Vis spectroscopy in addition to ion chromatography (IC) analyses. Among the purification processes, adsorption was found to be the best, showing a final purity of 99.8% based on relative quantification by IC. Thermal analysis revealed an exothermic temperature of $148^{\circ}C$ for the synthesized liquid monopropellant, but rose to $188^{\circ}C$ when urea was added.

• Korean Journal of Clinical Laboratory Science
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• v.53 no.1
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• pp.1-10
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• 2021

Radiopharmaceuticals are drugs that contain radioisotopes and are used in the diagnosis, treatment, or investigation of diseases. Radiopharmaceuticals must be manufactured in compliance with good manufacturing practice regulations and subjected to quality control before they are administered to patients to ensure the safety of the drug. Radiopharmaceuticals for administration to humans need to be sterile and pyrogen-free. Hence, sterility tests and membrane filter integrity tests are carried out to confirm the asepticity of the finished drug product, and a bacterial endotoxin test conducted to assess contamination, if any, by pyrogens. The physical appearance and the absence of foreign insoluble substances should be confirmed by a visual inspection. The chemical purity, residual solvents, and pH should be evaluated because residual by-products and impurities in the finished product can be harmful to patients. The half-life, radiochemical purity, radionuclidic purity, and strength need to be assessed by analyzing the radiation emitted from radiopharmaceuticals to verify that the radioisotope contents are properly labeled on pharmaceuticals. Radiopharmaceuticals always carry the risk of radiation exposure. Therefore, the time taken for quality control tests should be minimized and care should be taken to prevent radiation exposure during handling. This review discusses the quality control procedures and acceptance criteria for a diagnostic radiopharmaceutical.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2001.11b
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• pp.1365-1369
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• 2001

ISO/TC 108은 진동, 기름 순도(purity), 열 변화 및 전류 변동과 같은 요소들을 이용한 기계상태의 전반적인 감시와 평가를 위한 지침을 제공하기 위한 의도로 일련의 규격을 개발하는 과정 중에 있다. (중략)

• 한국신재생에너지학회:학술대회논문집
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• 2011.05a
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• pp.111.2-111.2
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• 2011

야금학적 방법을 통한 태양전지용 실리콘 제조를 위하여 아크로(Arc furnace)에서 제조된 용융 상태의 금속급 실리콘을 슬래그와 직접 반응시켜 불순물을 제거하는 공정에 관한 연구를 수행하였다. 이를 위해 아크로와 고주파 유도용해로(High-frequency induction furnace)를 이용하여 금속급 실리콘을 제조와 정련 특성 실험을 수행하였다. 본 연구에서 금속급 실리콘을 제조하기 위한 장비로 150kW급-DC 아크로와 300kW급-AC 아크로를 사용하였다. 원재료로 규석, 코크스(Cokes), 숯, 그리고 우드칩(Wood chip)을 실험 비율에 맞춰 아크로 내부에 장입하고, 이를 용융환원 방법을 통해 반응을 시켰다. 이때 생산된 금속급 실리콘의 순도는 약 99.2~99.8% 이었으며, 원재료의 순도, 장입 비율 및 아크로 운전 특성에 따라 편차가 있다. 아크로에서 생산된 금속급 실리콘의 경우 인(phosphorus), 붕소(boron)를 다량 함유하고 있고, 이를 제거하기 위하여 50kW급 고주파 유도용해로 장비를 사용하여 슬래그 정련 실험을 수행하였다. 슬래그 정련시 사용한 성분은 SiO2, CaO 그리고 CaF2 이며, 금속급 실리콘과 슬래그의 질량비 및 반응 시간에 따른 실리콘 불순물 특성을 평가하였다. 실험결과 인과 붕소는 각각 1 ppm 이하, 5 ppm 이하 였으며, 칼슘을 제외한 대부분의 금속 불순물의 경우 0.1~0.2% 임을 확인하였다.

• Journal of Hydrogen and New Energy
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• v.14 no.1
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• pp.81-95
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• 2003

본 연구는 압력균등화 공정이 추가된 2 컬럼 6 스뎁의 활성탄 PSA공정을 이용하여 비단열, 비등은 조건에서 메탄(80%)과 수소(20%)의 2성분계로부터 수소분리에 관한 연구이다. 공급가스의 압력, 흡착시간, 공급속도와 P/F 비율이 PSA공정에 미치는 영향에 대하여 평가했고 전산모사를 통해 최적조건을 구했다. 전산모사에 의한 최적 조건은 공급속도 17 LPM, 흡착압력 11 atm, P/F 비율이 0.07~0.1로 나타났으며, 이 조건으로부터 순도 99%, 회수율 85% 이상의 수소가스를 얻을 수 있었다.

• Resources Recycling
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• v.12 no.2
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• pp.36-44
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• 2003

The present work relates to the recovery of dissolved Mo from spent mandrel dissolving acid solution by injecting ammonia gas. In order to optimize the process parameters for high yield and high purity of recovered Mo products, a bench scale and a pilot scale experiments were carried out. As a result, more than 99.5% of Mo in spent acid was recovered in the form of ammonium molybdate(4MoO$_3$.$2NH_3$.$H_2$O). The purity of Mo products recovered was higher than 99.5%. In addition, the mother liquor, residual solution after precipitation and filtration of ammonium molybdate solid particles, could be utilized as fertilizers.

• Journal of the Korean Vacuum Society
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• v.12 no.2
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• pp.136-143
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• 2003

In this paper, high purity RF sputter-type ion source for non-mass separated ion beam deposition was evaluated. The fundamental characteristics of the ion source which is composed of an RF Cu coil and a high purity Cu target (99.9999 %) was studied, and the practical application of Cu thin films for ULSI metallization was discussed. The relationship between the DC target current and the DC target voltage at various RF power and Ar gas pressures was measured, and then preparation conditions for Cu thin films was described. As a result, it was found that the deposition conditions of the target voltage, the target current and the Ar pressure were optimized at -300 V, 240 W and 9 Pa, respectively. The resistivity of Cu films deposited at a bias voltage of -50 V showed a minimum value of 1.8 $\pm$ 0.1 $mu\Omega$cm, which is close to that of Cu bulk (1.67 $mu\Omega$cm).

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.90-95
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• 2003

Chemical management of annulus gas system is carried out for the purpose of ensuring the safety and reliability of the system via securing the integrity of the system, detecting the D$_2$O in-leakage of coolant and/or moderator, and reducing the radiation dose. Since the quality of CO_2$ gas, which is used as a filling gas for annulus gas system at CANDU plants, has a propound effect on the integrity of the system material and the radiation dose, CO_2$ gas of high quality is needed. If the quality of CO_2$ gas does not meet the specification, it may give rise to undesirable effect not only on the annulus gas system, but also on the environment due to the production of radioactive nuclei. Therefore, it is very important to check the impurities of CO_2$ gas. Based on this background, the inventories of C-14 and Ar-41 in CO_2$ gas that is supplied as annulus gas were estimated using the data on concentrations of the impurities of $CO_2$ such as C, N_2$ and Ar. The results of this study is expect to give useful information on optimization of CO_2$ impurities maintenance and management of gaseous radioactive wastes produced at CANDU plants.