• Radiation Oncology Journal
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• 제33권2호
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• pp.134-141
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• 2015

Purpose: This study investigates morphologic change of the rectosigmoid colon using a belly board in prone position and distended bladder in patients with rectal cancer. We evaluate the possibility of excluding the proximal margin of anastomosis from the radiation field by straightening the rectosigmoid colon. Materials and Methods: Nineteen patients who received preoperative radiotherapy between 2006 and 2009 underwent simulation in a prone position (group A). These patients were compared to 19 patients treated using a belly board in prone position and a distended bladder protocol (group B). Rectosigmoid colon in the pelvic cavity was delineated on planning computed tomography (CT) images. A total dose of 45 Gy was planned for the whole pelvic field with superior margin of the sacral promontory. The volume and redundancy of rectosigmoid colon was assessed. Results: Patients in group B had straighter rectosigmoid colons than those in group A (no redundancy; group A vs. group B, 10% vs. 42%; p = 0.03). The volume of rectosigmoid colon in the radiation field was significantly larger in group A (56.7 vs. 49.1 mL; p = 0.009). In dose volume histogram analysis, the mean irradiated volume was lower in patients in group B (V45 27.2 vs. 18.2 mL; p = 0.004). In Pearson correlation coefficient analysis, the in-field volume of rectosigmoid colon was significantly correlated with the bladder volume (R = 0.86, p = 0.003). Conclusion: Use of a belly board and distended bladder protocol could contribute to exclusion of the proximal margin of anastomosis from the radiation field.

• Journal of Mechanical Science and Technology
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• 제15권1호
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• pp.10-20
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• 2001

The leak before break(LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount(approximately 37.9 liters) containing the radioactive material which can activate the radiation detector device installed in near the heat exchanger is assumed. A postulated initial flaw size that can not grow to a critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural integrity of the heat exchanger is not impeded. Particularly the informational scenario presented in this paper discusses an actual nuclear plant.

• Nuclear Engineering and Technology
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• 제18권1호
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• pp.27-37
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• 1986

본 논문에서는 고리 1호기의 원자로 압력용기와 1차 콘크리트 차폐체 사이의 인자로 공동에서의 발사선 흐름 현상을 평가하였다. 원자로 압력용기 외부 표면에서 방출되는 누출 선속을 계산하기 위해 사용될 적합한 중성자 단면적 자료를 얻기 위하여, DLC-23/CASK, DLC-31/FEWG그리고 DLC-47/BUGLE 등 세 가지의 중성자 단면적 자료에 대한 검증 계산을 수행하였다. 누출 선속 계산은 ANISN으로 1차원적 계산을, DOT3.5로 2차원적 계산을 수행하였으며, 또한 원자로 공동에서의 방사선 흐름 현상을 분석하기 위하여, 알베도 개념이 도입된 몬테카를로 방법을 사용하는 MORSE-CG 전산 코드를 이용하여 3차원적 해석을 하였다. 그리고, 원자로 플랜지 부위에서의 방사화 분석을 수행하여 스터드 볼트의 방사화 정도를 평가하였다.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1483-1490
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• 2021

Many studies are undertaken into nuclear power plants (NPPs) in preparation for accidents exceeding design standards. In this paper, we analyze the applicability of various wireless communication technologies as accident countermeasures in different NPP environments. In particular, a commercial wireless communication module (WCM) is investigated by measuring leakage current and packet error rate (PER), which vary depending on the intensity of incident radiation on the module, by testing at a Co-60 gamma-ray irradiation facility. The experimental results show that the WCMs continued to operate after total doses of 940 and 1097 Gy, with PERs of 3.6% and 0.8%, when exposed to irradiation dose rates of 185 and 486 Gy/h, respectively. In short, the lower irradiation dose rate decreased the performance of WCMs more than the higher dose rate. In experiments comparing the two communication protocols of request/response and one-way, the WCMs survived up to 997 and 1177 Gy, with PERs of 2% and 0%, respectively. Since the request/response protocol uses both the transmitter and the receiver, while the one-way protocol uses only the transmitter, then the electronic system on the side of the receiver is more vulnerable to radiation effects. From our experiments, the tested module is expected to be used for design-based accidents (DBAs) of "Category A" type, and has confirmed the possibility of using wireless communication systems in NPPs.

• Journal of Radiation Protection and Research
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• 제6권1호
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• pp.34-40
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• 1981

방사선 치료를 위한 의료용 13 MeV 선형가속기를 설치 사용함에 따라 종사자에 대한 피폭방어를 비롯한 제반 설비구조의 설계가 중요하므로 저자들은 방사선 차폐벽과 시설구조를 법에 정해진 최대허용선량을 초과하지 않도록 계산하여 건축했으며 고에너지 선형가속기를 가동한 이후 실재 누출선량과 종사자의 피폭량을 측정하여 상호 검토하였다. 1) 방어벽의 계산은 NCRP #34 (1970)을 기초로 하였으며 이것이 가장 간단한 방법이고 경제적이었다. 2) 가속기 가동이후의 차폐벽으로부터 누출된 선량측정치는 계산에 의해 계획된 누출선량치의 약 $\frac{1}{5}$로 줄었으며 이는 치료환자의 수와 가장 안전한 수치를 사용했기 때문이었다. 3) 가속기에 의하여 방사선을 발생시키고 있는 동안 출입문 밖과 조종실 내에서의 누출선량율은 2-10mR/hr이었다. 4) 장시간 방사선을 발생시키거나 공기 조절장치의 성능이 약해졌을 때 치료실내의 오존냄새가 예측 의외로 심하였다.

• Journal of Korean Neurosurgical Society
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• 제54권3호
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• pp.175-182
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• 2013

Objective : Intracavitary injection of beta-emitting radiation source for control of cystic tumors has been tried with a benefit of localized internal radiation. The authors treated cystic brain tumor patients with Holmium-166-chitosan complex (Ho-166-chico), composed of a beta-emitting radionuclide Holmium-166 and biodegradable chit polymer, and evaluated the safety and effective measurement for response. Methods : Twenty-two patients with recurrent cystic brain tumor and/or located in a deep or eloquent area were enrolled in this pilot study. The cyst volume and wall thickness were determined on CT or MRI to assess radiological response. The activity of Ho-166-chico injected via Ommaya reservoir was prescribed to be 10-25 Gy to the cyst wall in a depth of 4 mm. Results : There was neither complications related to systemic absorption nor leakage of Ho-166-chico in all 22 patients. But, two cases of oculomotor paresis were observed in patients with recurrent craniopharyngioma. Radiological response was seen in 14 of 20 available follow-up images (70%). Seven patients of 'evident' radiological response experienced more than 25% decrease of both cyst volume and wall thickness. Another 7 patients with 'suggestive' response showed decrease of cyst volume without definitive change of the wall thickness or vice versa. All patients with benign tumors or low grade gliomas experienced symptomatic improvement. Conclusion : Ho-166-chico intracavitary radiation therapy for cystic tumor is a safe method of palliation without serious complications. The determination of both minimal effective dosage and time interval of repeated injection through phase 1 trial could improve the results in the future.

• 전자공학회논문지
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• 제50권6호
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• pp.85-90
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• 2013

본 논문에서는 본 연구실에서 제안된 Dummy Gate Assisted MOSFET을 이용하여 6bit SAR (Successive Approximation Register) ADC를 설계하였으며 이에 대한 대조군으로 Conventional MOSFET으로 동일한 회로를 설계하여 두 회로의 Co-60 Gamma Ray에 의한 누적방사선 영향을 비교 분석해 보았다. 설계된 SAR ADC는 Binary Capacitor DAC과 Dynamic Latch 형태의 Comparator 그리고 Logic으로 구성이 되었으며, 0.35um standard CMOS공정으로 제작되었다. 방사선 조사 후 Conventional MOSFET을 이용한 ADC는 정상동작하지 못하였지만, Dummy Gate Assisted MOSFET을 사용한 ADC는 방사선 조사 후 DNL은 0.7LSB에서 2.0LSB, INL은 1.8LSB에서 3.2LSB로 다소 증가하였으나 정상적인 A/D 변환이 가능하다는 것을 확인하였다.

• 한국전자파학회논문지
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• 제11권3호
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• pp.388-402
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• 2000

주기적인 구형격자를 갖는 유전체 코팅된 도체 실린더에 대해 무한 주기 구조와 유한 주기 구조에 대한 누설 파 안테나의 복사 특성을 이론적으로 해석하였다. 무한 주기 구조에 대하여는 모드 정합 법을 적용하여 해석하 였고, 유한 주기 구조에 대하여는 퓨리에 변환과 모드 전개를 사용하여 적분 방정식을 유도하고 선형 연립 방정 식을 얻는다. 구형격자의 폭, 깊이, 유전체 코팅두께, 도체 실린더의 반경, 유한 구형격자 개수의 영향이 위상 상 수, 누설 상수 및 복사패턴 등과 복사 특성에 미치는 영향을 조사하였고, 유한 주기 구조와 무한 주기 구조의 결 과를 비교하고 잘 일치함을 확인할 수 있었다. 균일 유한 주기 구형격자에 의한 높은 측엽을 줄이기 위해 안테나 의 전후단 부에 테이퍼링과 비균일 준주기 슬롯배열을 고려하였다. 또한 구형격자 표면파 안테나에 사용되는 구 형격자 주기. 폭, 깊이에 대해 테이퍼링을 통해 낮은 측엽을 갖는 endfire 복사패턴을 얻을 수 있었다.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2007년도 하계학술대회 논문집 Vol.8
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• pp.330-330
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• 2007

Polycrystalline mercuric iodide $HgI_2$) films are being developed as a new detector technology for digital x-ray imaging. The $HgI_2$ is generally vacuum deposited by physical vapor deposition (PVD) process. But the PVD thick deposition has been caused any instability in the biasing due to any defects or cracks. In this work we present a new particle-in-binder (PIB) methodologies used for the $HgI_2$ thick films. These growth techniques can be easily extended to produce much larger film areas. This paper, for the first time, presents results and comparison of polycrystalline $HgI_2$ films derived by various PIB methods. We investigated the structural and morphological properties of the films using X-ray diffraction (XRD) and scanning electron microscopy (SEM) analysis. The films were characterized with respect to their electrical properties and in response to x-ray photons. Physical and electrical results were also compared between conventional polycrystalline PVD and our detectors. Leakage current as low as $350\;pA/cm^2$ at the bias voltage of ~ 200 V has been observed. And high sensitivity and good linearity in the response to x-rays was obtained in the film derived by PIB sedimentation method. Our future efforts will concentrate on optimization of film growth techniques for uniform large area deposition on image readout arrays.

• 한국압력기기공학회 논문집
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• 제18권2호
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• pp.43-49
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• 2022

The purpose of this study is to evaluate the radiation effect on damage when the external shield of the spent nuclear fuel transport cask is damaged due to impact as the cause of an unexpected accident. The neutron and gamma-ray intensities and spectra are calculated using the ORIGEN-Arp module in the SCALE 6.2.4 code package⁽¹⁾ and then using MCNP6.2⁽²⁾ code calculate the dose rate. In order to evaluate the radiation dose according to the size of damage caused by external impact, various sized holes of 0.3~13.7% are assumed in the outer shield of the cask to evaluate the sensitivity to the dose. In the case of radiation source leakage, damage to the nuclear fuel assembly is assumed to be up to 6% based on overseas test cases. When only the outer shield is damaged, the maximum surface dose is calculated as 3.12E+03 mSv/hr. However, if the radiation source is leaked due to damage to the nuclear fuel assembly, it becomes 7.00E+05 mSv/hr which is about 200 times greater than the former case.