• 한국방사선학회논문지
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• 제17권3호
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• pp.481-487
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• 2023

본 연구에서는 15 MV를 이용한 전립샘암의 세기조절방사선치료 시 빔의 개수에 따른 광중성자선량의 부작용 발생률을 분석하고자 한다. 전립샘암 세기조절방사선치료의 방사선치료계획설계는 1회 처방선량 220 cGy, 전체 치료 횟수는 33회로 총 7260 cGy로 수립하였다. 실험에 사용된 선형가속기는 Varian의 True Beam STx(Varian, USA)이며, 계획용 표적체적(Planning target volume; PTV)에 15 MV로 광중성자 선량이 발생되도록 하였다. 치료계획의 설계는 Eclipse System (Varian Ver 10.0, USA)을 사용하여 세기조절방사선치료 5, 7, 9 portals로 하였다. 광중성자 선량 측정을 위해 광자극발광선량계 (Optically stimulated luminescence albedo neutron dosimeter, Landauer Inc., USA)를 사용하였다. 세기조절방사선치료 5 portals 시 1,000명당 1.7명, 7 portals 시 1,000명당 1.8명, 9 portals 시 1,000명당 2.0명이 광중성자 선량으로 인하여, 갑상샘에 부작용을 나타낼 확률임을 산출하였다. 본 연구는 세기조절방사선치료 시 2차 피폭선량의 위험성을 연구하여, 향후 방사선의 확률적 영향과 관련된 의미 있는 자료로 활용될 수 있기를 기대한다.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.130-141
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• 2020

Background: Concrete activation in cyclotron vaults is a major concern associated with their decommissioning because a considerable amount of activated concrete is generated by secondary neutrons during the operation of cyclotrons. Reducing the amount of activated concrete is important because of the high cost associated with radioactive waste management. This study aims to investigate the capability of the neutron absorbing materials to reduce concrete activation. Materials and Methods: The Particle and Heavy Ion Transport code System (PHITS) code was used to simulate a cyclotron target and room. The dimensions of the room were 457 cm (length), 470 cm (width), and 320 cm (height). Gd₂O₃, B₄C, polyethylene (PE), and borated (5 wt% ^natB) PE with thicknesses of 5, 10, and 15 cm and their different combinations were selected as neutron absorbing materials. They were placed on the concrete walls to determine their effects on thermal neutrons. Thin B₄C and Gd₂O₃ were placed between the concrete wall and additional PE shield separately to decrease the required thickness of the additional shield, and the thermal neutron flux at certain depths inside the concrete was calculated for each condition. Subsequently, the optimum combination was determined with respect to radioactive waste reduction, price, and availability, and the total reduced radioactive concrete waste was estimated. Results and Discussion: In the specific conditions considered in this study, the front wall with respect to the proton beam contained radioactive waste with a depth of up to 64 cm without any additional shield. A single layer of additional shield was inefficient because a thick shield was required. Two-layer combinations comprising 0.1- or 0.4-cm-thick B₄C or Gd₂O₃ behind 10 cm-thick PE were studied to verify whether the appropriate thickness of the additional shield could be maintained. The number of transmitted thermal neutrons reduced to 30% in case of 0.1 cm-thick Gd₂O₃+10 cm-thick PE or 0.1 cm-thick B₄C+10 cm-thick PE. Thus, the thickness of the radioactive waste in the front wall was reduced from 64 to 48 cm. Conclusion: Based on price and availability, the combination of the 10 cm-thick PE+0.1 cmthick B₄C was reasonable and could effectively reduce the number of thermal neutrons. The amount of radioactive concrete waste was reduced by factor of two when considering whole concrete walls of the PET cyclotron vault.

• Journal of Radiation Protection and Research
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• 제7권1호
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• pp.34-48
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• 1982

본 연구의 일차적 목적은 방사선 방호를 위하여 임의지점(任意地點)의 주변 방사선량의 수준을 특성(特性)짓는 방법의 하나로 ICRU가 정의(定義)한 흡수선량지수를 실측(實測)하는데 있는 바 이를 위한 실험은 에비실험과 본 실험의 두 단계로 나누어 수행하였다. 예비단계의 실험에서는 30cm 지름의 polyethylene구(球)를 사용한 반면 본 실험에서는 인체조직등가물질(人體組織等價物質)의 구(球)를 제작하였으며 두 실험 모두 $^{137}Cs$ 및 $^{60}Co$ 감마선장(線場)과 TRIGA Mark-II 원자로의 열중성자(熱中性子) column의 중성자공장(中性子工場)에서 행하여졌다. 감마선 흡수선량측정에는 TCD-700 $(^{7}LiF)$ chip을, 중성자선량측정에는 Au 방사화박(放射化薄)과 함께 TLD chip도 사용하였는데 이 경우에는 감마선의 기여를 판별해 내기 위하여 TLD-600 $(^{6}LiF)$과 TLD-700을 동시에 사용하였다. 감마선 조사(照射)의 경우 구(球) phantom내(內) 흡수선량의 이론적 해석은 Burlin의 공동이론(空洞理論)에서 유도된 Erlich의 방법을 썼으며, 중성자 선량해석에는 fluence-KERMA 변환방법을 사용하였다. 이들 선량에 관하여서는 특히 자세히 설명하였다. 해석에 실험결과는 모두 통계적으로 처리 분석하였으며 특히 심부선량분포(深部線量分布)는 규격화(規格化)한 값을 사용하여 도표(圖表)로 나타내는 한편, 결론에서는 방사선방호용 지수량(指數量) 실측(實測)의 가능성과 난점(難點)을 설명하고 해결하여야 할 문제점들을 언급(言及)하였다.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2410-2414
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• 2020

Heavy ions have a high potential for destroying deep tumors that carry the highest dose at the peak of Bragg. The peak caused by a single-energy carbon beam is too narrow, which requires special measures for improvement. Here, carbon-12 (¹²C) ion with different energies has been used as a source for calculating the dose distribution in the water phantom, soft tissue and bone by the code of Monte Carlobased FLUKA code. By increasing the energy of the initial beam, the amount of absorbed dose at Bragg peak in all three targets decreased, but the trend for this reduction was less severe in bone. While the maximum absorbed dose per bone-mass unit in energy of 200 MeV/u was about 30% less than the maximum absorbed dose per unit mass of water or soft tissue, it was merely 2.4% less than soft tissue in 400 MeV/u. The simulation result showed a good agreement with experimental data at GSI Darmstadt facility of biophysics group by 0.15 cm average accuracy in Bragg peak positioning. From 200 to 400 MeV/u incident energy, the Bragg peak location increased about 18 cm in soft tissue. Correspondingly, the bone and soft tissue revealed a reduction dose ratio by 2.9 and 1.9. Induced neutrons did not contribute more than 1.8% to the total energy deposited in the water phantom. Also during ¹²C ion bombardment, secondary fragments showed 76% and 24% of primary 200 and 400 MeV/u, respectively, were present at the Bragg-peak position. The combined treatment of carbon ions with neutron or electron beams may be more effective in local dose delivery and also treating malignant tumors.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.452-459
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• 2023

The core power control is an important issue for the study of dynamic characteristics in China initiative accelerator driven subcritical system (CiADS), which has direct impact on the control strategy and safety analysis process. The CiADS is an experimental facility that is only controlled by the proton beam intensity without considering the control rods in the current engineering design stage. In order to get the optimized operation scheme with the stable and reliable features, the variation of beam intensity using the continuous and periodic control approaches has been adopted, and the change of collimator and the adjusting of duty ratio have been proposed in the power control process. Considering the neutronics and the thermal-hydraulics characteristics in CiADS, the physical model for the core power control has been established by means of the point reactor kinetics method and the lumped parameter method. Moreover, the multi-inputs single-output (MISO) logical structure for the power control process has been constructed using proportional integral derivative (PID) controller, and the meta-heuristic algorithm has been employed to obtain the global optimized parameters for the stable running mode without producing large perturbations. Finally, the verification and validation of the control method have been tested based on the reference scenarios in considering the disturbances of spallation neutron source and inlet temperature respectively, where all the numerical results reveal that the optimization method has satisfactory performance in the CiADS core power control scenarios.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2016년도 제50회 동계 정기학술대회 초록집
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• pp.425.1-425.1
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• 2016

고온의 플라즈마를 긴 펄스 및 장시간 연속운전 유지기술 개발 및 연구를 위해서는 플라즈마는 더욱 가열되어야 하고, 고온 고밀도의 플즈마 상태를 유지시켜야 한다. 이러한 고성능 플라즈마 개발은 향후 핵융합 에너지의 상용화를 위한 절대필수적 기반기술이다. 현재 KSTAR 토카막에서는 플라즈마를 가열하기 위한 장치들 중 하나로서, 출력 6 MW 급의 중성입자빔을 입사하는 NBI (Neutral Beam Injection) 가열장치가 설치 운영 중에 있다. 이 NBI 가열장치는 진공환경에서 고온, 고압, 고전압 방전 및 수냉 등이 작동 및 운전되고 있기 때문에, 구성 부품 들의 미세한 구조적 결함에도 장치의 치명적 failed로 이어질 수 있다. 이번 연구에서는 NBI 가열장치의 특성상 극한 운전 환경에 있는 진공용기 부품 중 하나 인 빔인출을 위한 가속 그리드 (accelerating grid)의 구조적 손상및 결함 여부를 고속중성자 이미지 기법을 적용하여 내부를 투시 진단하였다. 가속 그리드는 copper로 제작되었고, 빔인출을 위한 원형의 구멍과 냉각관을 가진 평면판 형태로 되었다. 본 연구에서 내부투시 및 진단할 수 있는 고속중성자 이미징 기법의 적용으로 진공용기 부품 및 장치의 구조적 결함 및 손상 여부를 판단 가능하다는 연구 결과를 얻었다.

• 대한기계학회논문집A
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• 제21권8호
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• pp.1270-1275
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• 1997

This paper concerns with the finite element analysis of reactor internals with structural faults. For investigating the influence of hold-down spring faults on dynamic characteristics of CSB (core support barrel), reactor internals of Ulchin-1 nuclear power plant are modeled using finite element method and simulated with artificial defects on the hold-down springs. To prove the validity of the finite element models, the calculated natural frequencies of CSB in normal state are compared with those from the measurement results, which shows good agreement. According to results of finite element analysis, CSB beam mode natural frequency decreases by 4.5% in the case of 10% partial relaxation of hold-down springs, and decreases by 18.4% in the case of 20%. The range of shell mode natural frequency change is within 5.3%.

• 한국산학기술학회논문지
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• 제6권1호
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• pp.54-57
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• 2005

반도체 소자 면적의 축소에 따라 중성자의 소프트 에러율은 집적회로 설계시 큰 문제점으로 대두되고 있다. 고전류 중성자 빔에 의한 가속 실험에서, 래치-업 현상은 소프트 에러 발생율의 정확한 예측을 방해하는 요소로 작용하고 있다. 본 연구는 SRAM 소자의 SER 가속 실험시 발생하는 래치-업에 대한 효과를 분석하였다. 2차원 소자 시뮬레이터를 이용한 시뮬레이션 환경하에서의 결과 깊은 p-well 구조의 기판이 이중 또는 삼중 well 구조에 비하여 양호한 래치-업 방지 효과를 나타내었다. 또한 접지에 대한 $V_{DD}$ 전력선까지의 거리를 최소화하는 것이 효과적인 설계 기법으로 평가되었다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2011년도 제41회 하계 정기 학술대회 초록집
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• pp.317-317
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• 2011

Enhanced ICRF (Ion Cyclotron Range of Frequency) ion heating of H-mode D(H) plasma will be tried in 2011 KSTAR experimental campaign. Minority heating is a main ion heating scheme in the ICRF. Its efficiency increases as the hydrogen minority ratio increases in deuterium plasmas. And it should be sustained at a lower level than the critical minority ratio. Consequently, it is important to elevate the critical ratio to maximize ion heating and it is possible by increasing the ion temperature or parallel wave number (k${\parallel}$) of the antenna. Increasing the k${\parallel}$ is not a good approach since the coupling efficiency decreases exponentially with regard to k${\parallel}$ as well. So the remaining method is to increase ion temperature by using NB (Neutral Beam). Ion heating fraction of NB increases as the electron temperature increases. Therefore, we will try to heat electron by using ECH together with NB ion heating before ICRF power injection. The ICRF heating efficiency will be compared with respect to several NB+ECH+ICRF heating combinations through several diagnostics such as XICS (Xray Imaging Crystal Spectroscopy), CES (Charge Exchange Spectroscopy) and neutron measurement. The theoretical background and the experimental results will be presented in more detail in the conference.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2008년도 하계학술대회 논문집 Vol.9
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• pp.232-233
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• 2008

The 4H-SiC schottky diodes treated by the various dry etch methods were fabricated and electrically characterized. The post etch process including an Inductively Coupled Plasma(ICP) etch and a Neutron Beam Etch(NBE) was performed after a high-temperature activation annealing without graphite cap in order to eliminate the damaged surface generated during the activation annealing. The reverse leakage current of diode treated by ICP was 1/35 times lower than that of the diode without any post etch at the anode bias of -100V, while the reverse leakage current of diode treated by NBE was 1/44 times lower at the same bias.