• Nuclear Engineering and Technology
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• 제52권3호
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• pp.647-653
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• 2020

Stainless steel is used commonly in nuclear applications for shielding radiation, so in this study, three different types of new stainless steel samples were designed and developed. New stainless steel compound ratios were determined by using Monte Carlo Simulation program Geant 4 code. In the sample production, iron (Fe), nickel (Ni), chromium (Cr), silicium (Si), sulphur (S), carbon (C), molybdenum (Mo), manganese (Mn), wolfram (W), rhenium (Re), titanium (Ti) and vanadium (V), powder materials were used with powder metallurgy method. Total macroscopic cross sections, mean free path and transmission number were calculated for the fast neutron radiation shielding by using (Geant 4) code. In addition to neutron shielding, the gamma absorption parameters such as mass attenuation coefficients (MACs) and half value layer (HVL) were calculated using Win-XCOM software. Sulfuric acid abrasion and compressive strength tests were carried out and all samples showed good resistance to acid wear and pressure force. The neutron equivalent dose was measured using an average 4.5 MeV energy fast neutron source. Results were compared to 316LN type stainless steel, which commonly used in shielding radiation. New stainless steel samples were found to absorb neutron better than 316LN stainless steel at both low and high temperatures.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2011년도 춘계학술대회
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• pp.676-677
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• 2011

초경합금 성형용 코어를 이용한 고온 압축 성형방식으로 제작되기 때문에 성형용 코어의 초정밀 연산 가공 및 코어면 코팅 기술 개발이 시급한 상황이다. 따라서 본 연구에서는 성형용 초경합금 코어의 연삭가공을 수행하고, 가공 완료된 성형용 코어의 가공면에 Re-Ir 코팅을 수해, 측정을 통하여 코팅면의 마찰 계수 변화에 대한 연구를 수행하였다.

• Bulletin of the Korean Chemical Society
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• 제27권8호
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• pp.1189-1193
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• 2006

In order to develop radiopharmaceuticals for targeting a serotonin receptor such as $5-HT_{1A}$, histidine-$C_n$-arylpiperazines (AP) (C = alkyl, n = 2, 3, 4) were prepared in five steps with yields of 25%, 37% and 51%, respectively, and radiolabeled with the $[^{99m}Tc(CO)_3(H_2O)+3]^+$. The $^{99m}Tc(CO)_3$-Histidine-Cn-APs were prepared with a high yield (>99%) and characterized as a tridentate complex with a neutral charge to pass through the blood-brain barrier (BBB). The rhenium complexes with $Re(CO)_3$ were also synthesised and comparative experiments were achieved to evaluate the nature of the $^{99m}Tc$ complexes.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2010년도 춘계학술대회
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• pp.828-829
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• 2010

초경합금 성형용 코어를 이용한 고온 압축 성형방식으로 제작되기 때문에 성형용 코어의 초정밀 연산 가공 및 코어면 코팅 기술 개발이 시급한 상황이다. 따라서 본 연구에서는 성형용 초경합금 코어의 연삭가공을 수행하고, 가공 완료된 성형용 코어의 가공면에 Re-Ir 코팅을 수해, 측정을 통하여 코팅면이 표면 조도에 미치는 영향에 대하여 연구를 수행하였다.

• 대한방사성의약품학회지
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• 제5권1호
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• pp.3-10
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• 2019

The activities per volume of $^{188}Re$ and $^{99m}Tc$ from their generators are dependent on the specific activity of their mother nuclides $^{188}W$ and $^{99}Mo$ respectively. After a particular lapse of time, the eluted RI activity is exponentially reduced and thus cannot satisfy the needs of clinical application. The purpose of this study is to develop a $^{188}Re$ and $^{99m}Tc$ concentration device with a compact size that can extend the period of use as well as conveniently concentrate the RI. We designed the concentration module by including two-different check valves that do not required any manual on-off operations. In these concentration process, cation exchange resin embedded with Ag and anion exchange resins were used. After completing the concentrating step, the recovering yield was identified to be more than 93% for $^{188}Re$ generators and 88% for $^{99m}Tc$ generators. Moreover, all these procedures were done within 5 min.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.669-673
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• 2023

Introduction: The crucial step in preclinical process of radiopharmaceutical production is internal dosimetry evaluation by different ways to realize radiobiological dose-response relationships and to extract the results for clinical use. Till now several bone-seeking radiopharmaceuticals have been developed for bone metastasis. Interesting features of bisphosphonates attracted attentions to them in the field of radiopharmaceutical therapy and studies on new generation of them have been doing too. Materials and methods: In this study, we used ZNA as representative of the third generation. The radiopharmaceutical ¹⁸⁸Re-ZNA was produced and its radiochemical purity was investigated. Then, the biological distribution of the produced radiopharmaceutical at 1, 2, 4 and 24 h after injection on different organs of mice were investigated. Finally, the absorbed dose of organs in the human body was assessed using the RADAR method. Results: The results show 96% radiochemical purity of the ¹⁸⁸Re-ZNA radiopharmaceutical. The amount of %ID/g in bone is 1.131% after 1 h and in 24 h it has a significant amount compared to other organs, that is 0.516%. Also dosimetric results show that the highest absorption dose is related to bone and the amount of this dose is 0.050 mGy/MBq. Conclusion: Considering the possibility of producing the ¹⁸⁸Re-ZNA radiopharmaceutical, as well as the proper distribution of this radiopharmaceutical in target and non-target organs and increasing the absorbed dose in bone, it can be concluded that this radiopharmaceutical can be useful in the "radiopharmaceutical therapy" in metastases.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1871-1877
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• 2023

The main goal of the coordinated project development of therapeutic radiopharmaceuticals of Y-90 and Re-188 is to exploit advancements in radionuclide production technology. Here, direct and indirect production methods with medium reactor and cyclotron are compared to evaluate derived neutron flux and production yield. First, nano-sized ¹⁸⁶W and ⁸⁹Y specimens are suspended in water in a quartz vial by FLUKA simulation. Then, the solution is irradiated for 4 days under 9E+14 n/cm2/s neutron flux of reactor. Also, a neutron activator including three layers-lead moderator, graphite reflector, and polyethylene absorbent- is simulated and tungsten target is irradiated by 60 MeV protons of cyclotron to generate induced neutrons for ¹⁸⁸W and ⁹⁰Sr production via neutron capture. As the neutron energy reduced, the flux gradually increased towards epithermal range to satisfy (n/2n,γ) reactions. The obtained specific activities at saturation were higher than the reported experimental values because the accumulated epithermal flux and nano-sized specimens influence the outcomes. The beta emitters, which are widely utilized in brachytherapy, appeal an alternative route to locally achieve a rational yield. Therefore, the proposed method via neutron activator may ascertain these broad requirements.

• 자원리싸이클링
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• 제24권5호
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• pp.56-62
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• 2015

폐 초내열합금으로부터 침출된 염산용액에서 레늄을 회수하기 위하여 용매추출법을 이용한 레늄의 분리연구를 수행하였다. 용매추출공정을 통해 수상은 레늄이 용해된 합성용액을 사용하고 추출제의 종류 및 농도, 수상의 pH, HCl의 농도, 불순물의 영향을 조사하는 연구를 진행하였다. 레늄의 원료로 Ammonium perrhenate ((APR), Aldrich, $NH_4ReO_4$)을 사용하였고, 수상에 존재하는 레늄을 유기상으로 추출하기 위해 추출제는 음이온추출제인 Alamine304-1, 양이온추출제인 Cyanex272과 $D_2EHPA$를 사용하였다. 음이온추출제인 Alamine304-1 사용시 레늄의 추출율이 99% 이상 나타났으며 수상의 pH 는 0-2 사이에서 99% 추출되었다. Alamine304-1의 농도를 0.1, 0.5, 1 및 2%으로 조절하여 추출실험한 결과, 농도가 증가함에 따라 추출율이 증가한다. 레늄용액에 알루미늄, 코발트, 바나듐을 첨가하여 용매추출법에 의해 분리 실험한 결과 레늄은 99.8 %으로 추출되었으나 기타 금속들은 거의 추출되지 않았다.

• 한국정밀공학회지
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• 제26권1호
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• pp.51-56
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• 2009

Recently, with the increasing lightness and miniaturization of high resolution camera phones, the demand for aspheric glass lens has increased because plastic and spherical lens are unable to satisfy the required performance. An aspheric glass lens is fabricated by the high temperature and pressure molding using a tungsten carbide molding core, so precision grinding and coating technology for the molding core surface are required. This study investigates the effect of diamond-like carbon (DLC) and rhenium-iridium (Re-Ir) coating For aspheric molding core surface. The grinding conditions of the tungsten carbide molding core were obtained by design of experiments (DOE) for application in the ultra precision grinding process of the tungsten carbide molding core of the aspheric glass lens used in 5 megapixel, $4{\times}$ zoom camera phone modules. A tungsten carbide molding core was fabricated under this grinding condition and coated with the DLC and Re-Ir coating. By measurements, the effect of DLC and Re-Ir coating on the form accuracy and surface roughness of molding coer was evaluated.

• 대한핵의학회지
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• 제32권5호
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• pp.425-432
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• 1998

목적: Re-188을 치료용 방사성핵종으로 사용하기 위하여 W-188/Re-188 발생기를 병원 내에서 사용할 때 발생기 정도관리에 관한 실험을 실시하였다. 대상 및 방법: 알루미나 컬럼을 사용한 W-188/Re-188 발생기를 대상으로 하여 약 300일간 정도관리 실험을 하였다. 생리식염수 20 ml을 사용하여 발생기로부터 Re-188을 용출한 후 Re-188 용출액의 방사화학적 순도를 보기 위하여 박층크로마토그라피를 실시하고 감마에너지 스펙트럼을 측정하였다. 발생기의 화학순도실험으로 알루미늄의 용출을 알루미늄 이온 확인 키트를 사용하여 확인하였다. Re-188 용출액에 불순물로 있을 수 있는 모핵종 W-188은 감마에너지 스펙트럼으로 확인하였다. Re-188 용출액의 pH를 측정하였으며 발열원 검사로 LAL 검사를 시행하였다. Re-188 용출액을 이온교환컬럼을 사용하여 농축하였다. 결과: 용출분획의 Re-188 방사능양을 전체 용출한 방사능 양에 대한 백분율로 계산하였을 때 $5{\sim}10 ml$ 사이의 용출액이 전체 방사능양의 약 76%를 차지하였다. W-188의 방사능에 대한 Re-188 용출액의 방사능비는 270일간 평균 $67.4{\pm}7.0%$였으며, 용출 간격을 3일 이상 두었을 때가 높았다. 용출한 Re-188의 방사화학적 순도는 거의 100%였으며, 감마에너지 스펙트럼상에서 정점은 $135{\sim}188 keV$ 사이에 나타났다. 알루미늄 유출은 없었으며, W-188의 유출 역시 없었다. Re-188 용출액의 pH는 3이었으며, 발열성물질은 검출되지 않았다. 이온교환컬럼을 사용하여 Re-188을 농축하였을 때 회수율은 87%였다. 결론: 이 연구에서 사용한 W-188/Re-188 발생기는 각종 임상연구에 사용하기에 충분한 수준의 정도관리 결과를 나타내었다.