• Nuclear Engineering and Technology
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• 제5권1호
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• pp.38-43
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• 1973

A $X_4$형분자인 C $H_4$, Si $H_4$, Ge $H_4$, C $F_4$, Si $F_4$ 및 Ge $F_4$의 양자 또는 불소원자핵의 spin과 분자의 회전사이의 상호작용의 크기를 나타내는 spin-rotation constant $c_{av}$ 를 분자선자기공명방법에 의하여 실험적으로 결정하였다. 강자장근사에 의한 Hamiltonian 은 W $m_{I}$ $m_{J}$=- $g_{I}$ $m_{I}$H- $g_{J}$ $m_{J}$H- $C_{av}$ $m_{I}$ $m_{J}$로 주어지며, $c_{av}$ 는 C tensor의 trace의 3분지 1이 된다. 원자핵자기공오곡선은 v=- $g_{I}$H- $c_{av}$ $m_{J}$로 주어지는 여러개의 회전광공오선의 중첩으로 이룩되며, 전체곡선은 Gauss곡선으로 근사하여 $c_{av}$ 값을 구하였다. 회전공오선은 v= $g_{J}$H- $C_{av}$ $m_{I}$로 주어지며, $m_{I}$는 0, $\pm$1, $\pm$2의 값을 갖는다. $c_{av}$ 의 크기는 인접하는 두 회전공오곡선사이의 진동수치로서도 구할수 있다. 본실험에서 원자핵공오과 회전공오 공히 이용되였다. $c_{av}$ 의 부호는 분자선자기공오실험에서 쓰이는 방법으로서, 양자화되여서 불균일자장에서 분리된 분자선을 진행하는 방향의 좌측 또는 우측에서 부분적으로 차단하면서, 공오곡선의 변화를 보는것으로, 결정된 부호 와 $c_{av}$ 의 크기는 다음과 같다. C $H_4$; -10.3$\pm$0.4kHz Si $H_4$; +3.71$\pm$0.08kHz / Ge $H_4$; +3.79$\pm$0.13kHz C $F_4$; -6.81$\pm$0.08kHz / Si $F_4$; -2.46$\pm$0.06kHz Ge $F_4$; -1.84$\pm$0.04kHz

• 한국의학물리학회지:의학물리
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• 제28권4호
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• pp.226-231
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• 2017

The aim is to investigate the spectra responsibilities of QD (Quantum Dot) for the innovation of new dosimetry application for therapeutic Megavoltage X-ray range. The unique electrical and optical properties of QD are expected to make it a good sensing material for dosimeter. This study shows the spectra responsibility of toluene based ZnCd QD and PPO (2.5-diphenyloxazol) mixed liquid scintillator. The QDs of 4 sizes corresponding to an emission wavelength (ZnCdSe/ZnS:$440{\pm}5nm$, ZnCdSeS:470, 500, $570{\pm}5nm$) were utilized. A liquid scintillator for control sample was made of toluene, PPO. The Composition of QD loaded scintillators are about 99 wt% Toluene as solvent, 1 wt% of PPO as primary scintillator and 0.05, 0.1, 0.2 and 0.4 wt% of QDs as solute. For the spectra responsibility of QD scintillation, they were irradiated for 30 second with 6 MV beam from a LINAC ($Infinity^{TM}$, Elekta). With the guidance of 1.0 mm core diameter optical fiber, scintillation spectrums were measured by a compact CCD spectrometer which could measure 200~1,000 nm wavelength range (CCS200, Thorlabs). We measured the spectra responsibilities of QD loaded organic liquid scintillators in two scintillation mechanisms. First was the direct transfer and second was using wave shifter. The emission peaks from the direct transfer were measured to be much smaller luminescent intensity than based on the wavelength shift from the PPO to QDs. The emission peak was shifted from PPO emission wavelength 380 nm to each emission wavelength of loaded QD. In both mechanisms, 500 nm QD loaded samples were observed to radiate in the highest luminescence intensity. We observed the spectra responsibility of QD doped toluene based liquid scintillator in order to innovate QD dosimetry applicator. The liquid scintillator loading 0.2 wt% of 500 nm emission wavelength QD has most superior responsibility at 6 MV photon beam. In this study we observed the spectra responsibilities for therapeutic X-ray range. It would be the first step of innovating new radiation dosimetric methods for radiation treatment.

• Radiation Oncology Journal
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• 제34권4호
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• pp.265-272
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• 2016

Purpose: The purpose of this study is to evaluate the treatment outcomes of adjuvant radiotherapy using vaginal brachytherapy (VB) with a lower dose per fraction and/or external beam radiotherapy (EBRT) following surgery for patients with stage I endometrial carcinoma. Materials and Methods: The subjects were 43 patients with the International Federation of Gynecology and Obstetrics (FIGO) stage I endometrial cancer who underwent adjuvant radiotherapy following surgery between March 2000 and April 2014. Of these, 25 received postoperative VB alone, while 18 received postoperative EBRT to the whole pelvis; 3 of these were treated with EBRT plus VB. The median EBRT dose was 50.0 Gy (45.0-50.4 Gy) and the VB dose was 24 Gy in 6 fractions. Tumor dose was prescribed at a depth of 5 mm from the cylinder surface and delivered twice per week. Results: The median follow-up period for all patients was 57 months (range, 9 to 188 months). Five-year disease-free survival (DFS) and overall survival (OS) for all patients were 92.5% and 95.3%, respectively. Adjuvant radiotherapy was performed according to risk factors and stage IB, grade 3 and lymphovascular invasion were observed more frequently in the EBRT group. Five-year DFS for EBRT and VB alone were 88.1% and 96.0%, respectively (p = 0.42), and 5-year OS for EBRT and VB alone were 94.4% and 96%, respectively (p = 0.38). There was no locoregional recurrence in any patient. Two patients who received EBRT and 1 patient who received VB alone developed distant metastatic disease. Two patients who received EBRT had severe complications, one each of grade 3 gastrointestinal complication and pelvic bone insufficiency fracture. Conclusion: Adjuvant radiotherapy achieved high DFS and OS with acceptable toxicity in stage I endometrial cancer. VB (with a lower dose per fraction) may be a viable option for selected patients with early-stage endometrial cancer following surgery.

• 대한핵의학회지
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• 제25권2호
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• pp.286-293
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• 1991

$^{123}I$, which is applied for the thyroid and other in vivo kinetic study, has a special role in life sciences. The 159 KeV $\gamma-ray$ from $^{123}I$ is almost ideally appropriate for the current imaging instrumentation. Its decay mode (electron capture) and short half-life (13.3 hr) reduced the burden of radiation dose to the patients, and its chemical property makes it easy to synthesize the labelling compounds. In this experiment, the production of $^{123}I$ via the nuclear reaction $^{124}Te(p,2n)^{123}I$ with 28 MeV protons was sutdied. $TeO_2$ is used as a target material, because it has good physical properties. The target was prepared with $TeO_2$ powder and was molten into a ellipsoidal cavity (a=14 mm, b=10 mm, $270.8mg/cm^2$ thick) of pure platinum. The irradiation was carried out in the external proton beam with incident energies range from 28 MeV to 22 MeV, and current was $30{\mu}A$. The loss of $TeO_2$ target was significantly reduced by using $4\pi-cooling$ system in irradiation. The dry distillation method was adopted for the separation of $^{123}I$ from irradiated target, and when it was kept 5 minutes at $780^{\circ}C$, its result was quantitative. The loss of the target material $(TeO_2)$ was below 0.2% for each production run and $^{123}I$ from the dry distillation apparatus was captured with 0.01 N NaOH in $Na^{123}I$ form, then the pH of the solution was adjusted to $7.5\sim9.0$ with HC1/NaOH. The $Na^{123}I$ solution was passed through $0.2{\mu}m$ membrane filter, and sterilized under high pressure and temperature for 30 minutes. The production of $^{123}I$ is acceptable for clinical application based on the quality of USP XXI.

• Radiation Oncology Journal
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• 제29권3호
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• pp.156-163
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• 2011

Purpose: To evaluate long-term local control rate and toxicity in patients treated with external beam radiotherapy (EBRT) for pituitary adenomas. Materials and Methods: We retrospectively reviewed the medical records of 60 patients treated with EBRT for pituitary adenoma at Korea University Medical Center from 1996 and 2006. Thirty-five patients had hormone secreting tumors, 25 patients had non-secreting tumors. Fifty-seven patients had received postoperative radiotherapy (RT), and 3 had received RT alone. Median total dose was 54 Gy (range, 36 to 61.2 Gy). The definition of tumor progression were as follows: evidence of tumor progression on computed tomography or magnetic resonance imaging, worsening of clinical sign requiring additional operation or others, rising serum hormone level against a previously stable or falling value, and failure of controlling serum hormone level so that the hormone level had been far from optimal range until last follow-up. Age, sex, hormone secretion, tumor extension, tumor size, and radiation dose were analyzed for prognostic significance in tumor control. Results: Median follow-up was 5.7 years (range, 2 to 14.4 years). The 10-year actuarial local control rates for non-secreting and secreting adenomas were 96% and 66%, respectively. In univariate analysis, hormone secretion was significant prognostic factor (p = 0.042) and cavernous sinus extension was marginally significant factor (p = 0.054) for adverse local control. All other factors were not significant. In multivariate analysis, hormone secretion and gender were significant. Fifty-three patients had mass-effect symptoms (headache, dizziness, visual disturbance, hypopituitarism, loss of consciousness, and cranial nerve palsy). A total of 17 of 23 patients with headache and 27 of 34 patients with visual impairment were improved. Twenty-seven patients experienced symptoms of endocrine hypersecretion (galactorrhea, amenorrhea, irregular menstruation, decreased libido, gynecomastia, acromegaly, and Cushing's disease). Amenorrhea was abated in 7 of 10 patients, galactorrhea in 8 of 8 patients, acromegaly in 7 of 11 patients, Cushing's disease in 4 of 4 patients. Long-term complication was observed in 4 patients; 3 patients with cerebrovascular accident, 1 patient developed dementia. Of these patients, 3 of 4 received more than 60 Gy of irradiation. Conclusion: EBRT is highly effective in preventing recurrence and reducing mass effect of non-secreting adenoma. Effort to improve tumor control of secreting adenoma is required. Careful long-term follow-up is required when relatively high dose is applied. Modern radiosurgery or proton RT may be options to decrease late complications.

• 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.

• 한국의학물리학회지:의학물리
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• 제23권4호
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• pp.209-218
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• 2012

최근 방사선치료기기 및 방사선치료기술이 빠르게 발전하고 복잡해짐에 따라 방사선치료의 신뢰성을 높이고 정확한 환자 치료와 환자 및 치료관련 종사자의 방사선안전을 확보하기 위하여 자격있는 의학물리사 적정 인원에 대한 재평가가 이루어지고 있다. 방사선치료분야에서 의학물리사의 적정한 인원수준에 대하여 외국의 연구사례 및 결과에 대해 미국과 유럽을 중심으로 분석하였다. 또한 외국연구결과를 토대로 국내에 필요한 의학물리사의 적정 인원을 간접적으로 계산해 보았다. 국내 중대형 6개 병원의 현재 의학물리사 적정 인원은 국제적 적정 권고 인원의 50% 이하였다. 더욱 더 객관적인 의학물리사의 필요 인원수를 예측하기 위하여는 국내 여건에 적합한 추가적인 연구가 요구되며, 특히 지속적으로 증가되고 있는 입자방사선치료를 고려한 인원수 예측이 필요하다.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2935-2940
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• 2023

A polystyrene phantom was developed following the guidance of the International Atomic Energy Association (IAEA) for gamma knife (GK) quality assurance. Its performance was assessed by measuring the absorbed dose rate to water and dose distributions. The phantom was made of polystyrene, which has an electron density (1.0156) similar to that of water. The phantom included one outer phantom and four inner phantoms. Two inner phantoms held PTW T31010 and Exradin A16 ion chambers. One inner phantom held a film in the XY plane of the Leksell coordinate system, and another inner phantom held a film in the YZ or ZX planes. The absorbed dose rate to water and beam profiles of the machine-specific reference (msr) field, namely, the 16 mm collimator field of a GK Perfexion^TM or Icon^TM, were measured at seven GK sites. The measured results were compared to those of an IAEA-recommended solid water (SW) phantom. The radius of the polystyrene phantom was determined to be 7.88 cm by converting the electron density of the plastic, considering a water depth of 8 g/cm². The absorbed dose rates to water measured in both phantoms differed from the treatment planning program by less than 1.1%. Before msr correction, the PTW T31010 dose rates (PTW Freiberg GmbH, New York, NY, USA) in the polystyrene phantom were 0.70 (0.29)% higher on average than those in the SW phantom. The Exradin A16 (Standard Imaging, Middleton, WI, USA) dose rates were 0.76 (0.32)% higher in the polystyrene phantom. After msr correction factors were applied, there were no statistically significant differences in the A16 dose rates measured in the two phantoms; however, the T31010 dose rates were 0.72 (0.29)% higher in the polystyrene phantom. When the full widths at half maximum and penumbras of the msr field were compared, no significant differences between the two phantoms were observed, except for the penumbra in the Y-axis. However, the difference in the penumbra was smaller than variations among different sites. A polystyrene phantom developed for gamma knife dosimetry showed dosimetric performance comparable to that of a commercial SW phantom. In addition to its cost effectiveness, the polystyrene phantom removes air space around the detector. Additional simulations of the msr correction factors of the polystyrene phantom should be performed.

• 한국방사선학회논문지
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• 제7권3호
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• pp.213-219
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• 2013

현재 국내에서 가동 중인 싸이클로트론센터는 약 35개소에 이르며, 대부분의 싸이클로트론 센터는 주로 핵의학검사용 악성종양 추적자인 $^{18}FDG$ 등과 같은 방사성의약품을 생산하고 있다. 18F을 생산하기 위한 타겟으로서 산소동위원소비($^{18}O/O$)가 98%정도인 고농축 $H_2{^{18}}O$를 사용하고 있다. 고농축 $H_2{^{18}}O$는 1 gram당 가격이 약 60~70 USD 정도로 매우 고가이나 100% 수입에 의존하고 있는 상황이다. 양성자 빔 조사 전의 타겟(고농축 $H_2{^{18}}O$)은 비방사성이다. 하지만, "사용후 $H_2{^{18}}O$"는 불순물들의 방사화에 의해 방사능을 띄게 되므로 방사선안전 법규에 따라 적절한 관리가 이루어져야 한다. 최근의 핵의학검사 건수의 증가에 따라 사용 후 O-18의 발생량이 증가하고 있음에도 불구하고 국내에서는 현재까지 이에 대한 방사화분석이 이루어지지 않았다. 따라서, 본 연구에서는 $^{18}F$생산을 위해 양성자조사를 하고 난 타겟, 이른바 "사용후 O-18 water"의 방사화 분석을 실시하여 핵종별 방사능농도(Bq/g)를 확인하고자 하였다. 세 곳의 서로 다른 싸이클로트론 센터에서 보관 중인 "used $H_2{^{18}}O$" 중 20g 씩을 채취한 3개의 시료에 대해 방사화분석을 실시하였으며, 분석결과 사용후 O-18 water는 감마선 방출 방사성핵종인 $^{56}Co$, $^{57}Co$, $^{58}Co$, $^{54}Mn$ 등과 베타선 방출핵종인 $^3H$을 상당량 포함하고 있음을 확인할 수 있었다. 또한, 모든 시료에서 3H은 규제면제 농도 이하인 반면, 한 개 시료는 핵종별 규제면제농도 이상의 감마선 방출핵종을 포함하고 있음을 확인하였다. 시료에 포함된 감마선 방출핵종의 방사능 농도(Bq/g)는 조사 후 보관기간의 차이에 따라 달랐으며, 향후의 추가적인 연구가 더 필요하다고 판단되지만, 본 연구의 결과는 "사용후 O-18 water"의 합리적인 관리방안 수립을 위한 근거 자료로 활용될 수 있을 것이다.

• Nuclear Medicine and Molecular Imaging
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• 제40권4호
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• pp.228-232
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• 2006

목적 : $[^{18}F]F_2\;(T_{1/2}=110\;min)$ 기체를 이용하여 친전자성 치환반응으로 방사성동위원소 $^{18}F$을 표지하는 방법은 새로운 앙전자방출단층촬영용 방사성의약품 개발 분야에서 유용하게 이용되고 있다. 그림에도 불구하고 $[^{18}F]F_2$를 높은 생산수율과 비방사능으로 생산하기 위한 표적 개발 연구는 아직도 진행 중에 있다. 본 연구에서는 친핵성 치환반응으로 $^{18}F$을 도입하기 어려운 방사성의약품에 친전자성 치환반응으로 방사성동위원소를 도입할 수 있는 $[^{18}F]F_2$ 가스의 효율적인 생산에 관해 연구하였다. 대상 및 방법: 표적은 원추형 모양의 알루미늄 재질로 제작하였다. $[^{18}F]F_2$ 생산을 위한 핵반응으로 $^{18}O(p,n)^{18}F$를 사용하였으며, two-step 빔 조사방법을 이용하였다. 첫 번째 조사는 농축 $[^{18}O]O_2$가스를 표적에 충진한 후 빔 조사하여 $^{18}O(p,n)^{18}F$ 핵반응을 일으킴으로써 $^{18}F$를 생산한다. 생산된 $^{18}F$은 표적 챔버 기벽에 흡착된다. $[^{18}O]O_2$은 재사용을 위하여 냉각포획법으로 회수하였으며, $^{18}F$를 회수하기 위해 $[^{19}F]F_2/Ar$ 가스를 충진한 후, 두 번째 빔을 조사하여 방사성불소를 회수하는 방법으로 구성된다. 본 연구에서는 최적의 방사성불소 생산 조건을 찾기 위해 빔 조사 시간, 빔 전류 세기 농축 $[^{18}O]O_2$ 충진 압력 등의 변화에 따라 생산량을 평가하였다. 결과: 빔 조사 시간, 빔 전류, 농축 $[^{18}O]O_2$ 충진 압력 등의 조건을 변화시키면서 생산량을 평가한 결과 최적의 빔 조사 조건은 다음과 같다. 첫 번째 조사: 농축 $[^{18}O]O_2$을 약 15.0 bar충진, 13.2 MeV, 30 ${\mu}A$로 60-90분 조사; 두 번째 조사: 1% $[^{19}F]F_2/Ar$혼합가스 12.0 bar 충진, 13.2 MeV, 30 ${\mu}A$로 20-30분 조사 후 아르곤 가스로 회수하였을 때 EOB(end of bombardment) 기준으로 약 $34{\pm}6.0$ GBq(n>10)의 $[^{18}F]F_2$를 얻었다. 결론: $^{18}O(p,n)^{18}F$ 핵반응을 이용하여 친전자성 방사성동위원소 $[^{18}F]F_2$를 생산하였다. 표적 챔버는 알루미늄으로 제작하였으며 본 연구에서 연구된 $[^{18}F]F_2$가스는 친핵성 치환반응으로 방사성동위원소를 도입하기 어려운 다양한 방사성의 약품개발에 유용하게 이용될 수 있을 것이다.