• Proceedings of the Korean Vacuum Society Conference
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• 2000.02a
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• pp.189-189
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• 2000

고분자 재료에 이온을 주입함으로서 경도, 내마모, 내피로성의 기계적인 특성과 내부식성 등의 화학적 특성이 향상되며, 표면 전기전도도와 광학밀도(optical density)가 변한다. 본 연구에서는 MPPO(Modified-Polyphenlene Oxide) 표면에 N2, Ar, Xe 이온을 에너지 50keV, 선량(dose)을 1$\times$1015에서 1$\times$1017ions/cm2로 증가시키면서 조사하였다. 이온 조사량의 증가에 따라 표면 저항이 2$\times$1015에서 6$\times$106($\Omega$/$\square$)으로 감소하여 표면 전기전도도가 향상되었다. Ar 이온은 1016ion/cm2이하의 조사량(dose)에서 N2보다 표면 저항을 더 많이 감소하는데 반해 1016ion/cm2 이상의 조사량에서는 Ar과 N2의 표면 저항이 비슷한 값을 나타냈다. Xe은 Ar과 N2이온에 비하여 전체적으로 표면저항이 많이 감소하여 전도도의 향상은 Xe, Ar, N2 순서로 질량이 큰 이온이 조사 효과가 큰 것으로 나타났다. 소재 표면은 SIMS 분석을 통하여 깊이에 따른 주입이온의 분포를 관찰하였으며, 표면 색상은 황색에서 갈색을 거쳐 암갈색으로 변화함으로서 가시광선에 대한 반사율(reflectance)이 감소하고 광학밀도(optical density)가 증가하여 광학적 특성이 변하였다. 이온 주입 후 에너지 전이에 의한 효과는 optical gap를 감소시켜 광학밀도(optical density)와 표면 전기 전도도를 증가시킨다. 이에 따라 본 논문에서는 이온주입에 의한 광학적, 전기적 특성간의 상관관계를 밝히고자 한다.

• Journal of IKEEE
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• v.27 no.3
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• pp.303-307
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• 2023

In this paper, the creation of an Electron-Hole Pair due to Total Ionizing Dose (TID) effects inside the oxide of a Buried Channel Array Transistor (BCAT) device is induced, resulting in an increase in leakage current and threshold due to an increase in hole trap charge at the oxide interface. By comparing and simulating changes in voltage with the previously proposed Partial Isolation Buried Channel Array Transistor (Pi-BCAT) structure, the characteristics in leakage current and threshold voltage changed regardless of the increased oxide area of the Pi-BCAT device, compared to the asymmetrically doped BCAT structure. It shows superiority.

• Journal of Radiation Industry
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• v.17 no.2
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• pp.135-141
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• 2023

Tritium is used in various types of parts such as luminous bodies. These parts are maintained for inspection and replacement at a facility licensed to use radioactive isotopes. This study analyzed the concentration of tritium in working facilities to supplement and develop the safety management system for the maintenance environment of parts containing tritium. In addition, the internal exposure dose was evaluated to analyze the effects of leaked tritium when continuously exposed to workers. As a result of evaluating the internal exposure dose for workers for 30 days, the maximum was 9.70 μSv and the average was 1.45 μSv. Based on the results of this study, the internal radiation exposure safety of workers handling parts containing tritium was confirmed, and additional protective measures to prevent unnecessary exposure to tritium were suggested. This study is expected to contribute to supplementing and developing the radiation safety management system.

• Progress in Medical Physics
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• v.19 no.4
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• pp.263-268
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• 2008

The application of a respiratory gated radiotherpy method to the lung radiation surgery was evaluated compared with the conventional method in which the whole tumor motion range is considered in the delineation of PTV (Planning target volume). The four dimensional CT simulation images were acquired for the five NSCLC (Non-small cell lung cancer) patients for radiation surgery. The respiratory gated plan was prepared with the 50% phase CT images and the conventional method was planned based on the ITV (Internal target volume) which include all the target volumes created in each phase CT images within a whole respiratory period. The DVH (Dose volume histogram) of OAR (Organ at risk) which calculated in each method was compared for the evaluation of the plan properness. The relative decrease of OARs' DVH were verified in the application of respiratory gated method. The average decrease rate were $16.88{\pm}9.97%$ in the bronchus, $34.13{\pm}19.15%$ in the spinal cord, $28.42{\pm}18.49%$ in the chest wall and $32.48{\pm}16.66%$ in the lung. Based on these results, we can verified the applicability and the effectiveness of the respiratory gated method in the lung radiation surgery.

• The Korean Journal of Nuclear Medicine
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• v.29 no.3
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• pp.343-349
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• 1995

Background : For biological dosimetry of radiation exposure, both observing hematologic change and calculating Ydr by chromosomal analysis as biological indicators are widely used. However, due to the lack of studies on biological dosimetry of radiation dose absorbed in the body such as in the cases of radioactive iodine therapy, the maximal and safe dose is not well known, nor is the extent to which the body can safely endure radiation exposure. Purpose : To investegate the practical applicability of hematologic changes and Ydr as an indicator for estimating radiation exposure, to patients with thyroid diseases after doses of radioactive iodine. Material and Methods : 5 patients with hyperthyroidism and 35 patients who have had thyroid cancer operation were under treatment with radioactive iodine, changes in number of lymphocytes were tracked and Ydr was calculated for more than 2 months by chromosomal analysis in peripheral lymphocytes. Results ; 1) The number of lymphocytes began to decrease 2 weeks after doses of radioactive iodine, and reached the nadir after 6 and 8 weeks, then gradually recovered. 2) The nadir count of lymphocytes was reversely correlated with the administered dosage of radioactive iodine. 3) Ydr was generally stable between 2 and 8 weeks. 4) The maximal value of Ydr was correlated with the administered dosage of radioactive iodine. 5) Ydr value at the 2nd week increased with augmented dosage of radioactive iodine. 6) Ydr value at the 2nd week was correlated with fall of lymphocyte count. Conclusion : Patients must be closely observed, because temporary bone marrow suppression and slight chromosomal aberration can be produced by even generally used dosages of radioactive iodine for diagnosis and therapy. Maximal percent fall of lymphocyte count, Ydr at the 2 week interval and maximal Ydr can be used as the biological predictor of administered dosage of radioactive iodine.

• Progress in Medical Physics
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• v.20 no.1
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• pp.37-42
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• 2009

Proton therapy facility, which is recently installed at National Cancer Center in Korea, generally produces a large amount of radiation near cyclotron due to the secondary particles and radioisotopes caused by collision between proton and nearby materials during the acceleration. Although the level of radiation by radioisotope decreases in length of time, radiation exposure problem still exists since workers are easily exposed by a low level of radiation for a long time due to their job assignment for maintenance or repair of the proton facility. In this paper, the working environment near cyclotron, where the highest radiation exposure is expected, was studied by measuring the degree of radiation and its duration for an appropriate level of protective action guide. To do this, we measured the radiation change in the graphite based energy degrader, the efficiency of transmitted beam and relative activation degree of the transmission beam line. The results showed that while the level of radiation exposure around cyclotron and beam line during the operation is much higher than the other radiation therapy facilities, the radiation exposure rate per year is under the limit recommended by the law showing 1~3 mSv/year.

• Journal of Radiation Protection and Research
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• v.38 no.3
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• pp.143-148
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• 2013

Operational nuclear facilities such as nuclear power plants and particle accelerators show various neutron spectra according to the type of facilities and specific position. Necessities of neutron dose management and neutron monitoring for radiation protection of radiation workers in such a kind of facilities have continuously increased in recent years. Bonner sphere spectrometers are widely used for measurement of neutron spectra. Data on response function of neutron detector, default neutron spectra and count rates of Bonner sphere spectrometer are required to obtain unfolded neutron spectra in specific workplaces. In this study, we carried out measurement of neutron spectra produced in MC50 cyclotron using Bonner sphere spectrometer with LiI scintillation detector. Additionally, we estimated quantitative data on neutron flux, mean neutron energy and ambient dose equivalent rate according to the incident proton energies and positions in MC50 cyclotron.

• Journal of Radiation Protection and Research
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• v.35 no.1
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• pp.21-25
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• 2010

Burnup of spent fuel should be determined accurately for the safety control of spent fuel. Especially, it is necessary to measure the burnup profile along the nuclear fuel axis. In the present work, an ionization chamber was designed and fabricated to measure the gamma ray profile inside the guide tube of spent fuel. The ionization chamber was composed of three parts; induction part, gas-inlet part, and sensor part. The sensor part had two electrodes; cathode and anode. A guide electrode was considered in the ionization chamber design to make the ionization chamber to be inserted easily into the guide tube. Pure gas (argon and xenon) was inserted into the ionization chamber, and the leakage current and saturation curve were measured to determine the operation characteristics of the ionization chamber. The gamma ray radiation was also measured in relatively high dose environment. The gamma ray profile of the spent fuel will be measured with the ionization chamber.

• Proceedings of the Korea Crystallographic Association Conference
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• 2003.05a
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• pp.22-22
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• 2003

원자로에서 핵분열에 의해 생성된 고에너지 중성자는 감속재를 통해 열평형에 의해 에너지가 낮춰져 통계적 분포, 즉 Maxwell-Boltzman 운동에 따른 에너지 스펙트림을 갖게 된다. 중성자 산란장치는 통상 단색빔을 이용하므로 단색기(monochiomator)를 통해 이 분포에서 특정 파장의 중성자빔을 인출, 즉 단색화한다. 이때 단색기는 각각의 중성자 산란장치에 사용할 수 있는 특정 파장의 중성자빔을 인출하면서도, 파장의 퍼짐을 적절하게 조절하여 높은 중성자속(neutron flux)을 가지며 분해능도 또한 좋아야 한다. 전통적으로 많이 사용하는 단색화 방법은 결정의 내부결함을 유도하여 만든 모자익(mosaic) 결정을 이용하는 것이다. 이 방법은 특정 파장을 얻으면서도 좋은 분해능과 높은 중성자속을 갖는 모자익 결정을 만들기가 어렵고, 한번 결정된 단색기의 특성을 바꿀 수 없는 단점이 있다. 1980년대부터 몇몇 그룹이 거의 완전하게 성장된 단결정 슬랩을 미세하게 구부려서 탄성변형을 주어 effective 모자익 구조를 발생시킨 '구부린 완전결정(bent perfect crystal, BPC)' 단색기를 개발하여 특정 목적에 활용하는 시도를 하였다. BPC 단색기는 단색화된 중성자빔을 집속(focusing)할 수 있으며, 결정의 구부림 정도를 조절하고 배치 기하를 바꿈으로써 다양한 특성을 갖는 단색빔을 얻을 수 있는 장점이 있다. 이렇게 단색기의 기하학적 변수를 조절함으로써 회절빔의 집속도와 분해능을 조절할 수 있어서 잔류응력 측정이나 단결정 회절 및 집합조직 측정장치 등에 적용할 수 있다. 본 연구에서는 BPC 단색기의 원리와 여러 배치기하에 따른 빔의 특성을 소개하고자 한다.빔이 시료와 상호 작용하는 면적과 상호작용하지 않을 때의 빔을 회절모드에서 faraday cup으로 측정한 빔전류로 부터 계산하였다. Gibbsite에 대한 전자빔 조사 시 1분 이내에 급격한 Hydroxyl Ion(OH-)의 이탈로 인해 Cibbsite의 구조는 거시적 비정질화가 되며 시간증가에 따라 χ-alumina → ν-alumina → σ-alumina or δ-alumina의 순으로 상전이를 겪는다. 전자빔 조사 시 관찰된 회절자료의 가시적 변화를 통해 illumination angle 1.25mrad(Dose rate : 334 × 10³ e/sup -//sec·n㎡)일 경우 약 3초 이내에 비정질화가 시작됨을 알 수 있었고 이는 약 1 × 10/sup 6/ e/sup -//sec·n㎡ 의 전자선량에 해당되며 이를 기준으로 각각의 illumination angle에 대한 임계전자선량을 평가할 수 있었다. 실질적으로 Cibbsite와 같은 무기수화물의 직접가열실험 시 전자빔 조사에 의해 야기되는 상전이 영향을 배제하고 실험을 수행하려면 illumination angle 0.2mrad (Dose rate : 8000 e/sup -//sec·n㎡)이하로 관찰하고 기록되어야 함을 본 자료로부터 알 수 있었다.운동횟수에 의한 영향으로써 운동시간을 1일 6시간으로 설정하여, 운동횟수를 결정하기 위하여 오전, 오후에 각 3시간씩 운동시키는 방법과 오전부터 6시간동안 운동시키는 두 방법을 이용하여 품질을 비교하였다. 각 조건에 따라 운동시킨 참돔의 수분함량을 나타낸 것으로, 2회(오전 3시간, 오후 3시간)에 나누어서 운동시키기 위한 육의 수분함량은 73.37±2.02%를 나타냈으며, 1회(6시간 운

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2012.05a
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• pp.719-721
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• 2012

In this study, we carried out transient radiation experiments for identify failure situation by a transient radiation effect on DC/DC converter device due to high energy ionizing radiation pulse induced to electronic device. This experiments were carried out using a 60 MeV electron beam pulse of the LINAC(Linear Accelerator) facility in the Pohang Accelerator Laboratory. In this experiment, we has found that the latch-up phenomena could be checked in more than $1.0{\times}10^8$rad(si)/sec condition.