• Asian Pacific Journal of Cancer Prevention
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• 제16권10호
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• pp.4251-4256
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• 2015

Background: Exposure to cigarette may affect human health and increase risk of a wide range of diseases including pulmonary diseases, such as chronic obstructive pulmonary disease (COPD), asthma, lung fibrosis and lung cancer. However, the molecular mechanisms of pathogenesis induced by cigarettes still remain obscure even with extensive studies. With systemic view, we attempted to identify the specific gene modules that might relate to injury caused by cigarette smoke and identify hub genes for potential therapeutic targets or biomarkers from specific gene modules. Materials and Methods: The dataset GSE18344 was downloaded from the Gene Expression Omnibus (GEO) and divided into mouse cigarette smoke exposure and control groups. Subsequently, weighted gene co-expression network analysis (WGCNA) was used to construct a gene co-expression network for each group and detected specific gene modules of cigarette smoke exposure by comparison. Results: A total of ten specific gene modules were identified only in the cigarette smoke exposure group but not in the control group. Seven hub genes were identified as well, including Fip1l1, Anp32a, Acsl4, Evl, Sdc1, Arap3 and Cd52. Conclusions: Specific gene modules may provide better understanding of molecular mechanisms, and hub genes are potential candidates of therapeutic targets that may possible improve development of novel treatment approaches.

• Asian Pacific Journal of Cancer Prevention
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• 제16권8호
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• pp.3365-3370
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• 2015

Radiotherapy has an important role in the treatment of prostate cancer. Three-dimensional conformal radiation therapy (3D-CRT), intensity modulated radiation therapy (IMRT) and volumetric modulated arc therapy (VMAT) techniques are all applied for this purpose. However, the risk of secondary radiation-induced bladder cancer is significantly elevated in irradiated patients compared surgery-only or watchful waiting groups. There are also reports of risk of secondary cancer with low doses to normal tissues. This study was designed to compare received volumes of low doses among 3D-CRT, IMRT and VMAT techniques for prostate patients. Ten prostate cancer patients were selected retrospectively for this planning study. Treatment plans were generated using 3D-CRT, IMRT and VMAT techniques. Conformity index (CI), homogenity index (HI), receiving 5 Gy of the volume (V5%), receiving 2 Gy of the volume (V2%), receiving 1 Gy of the volume (V1%) and monitor units (MUs) were compared. This study confirms that VMAT has slightly better CI while thev olume of low doses was higher. VMAT had lower MUs than IMRT. 3D-CRT had the lowest MU, CI and HI. If target coverage and normal tissue sparing are comparable between different treatment techniques, the risk of second malignancy should be a important factor in the selection of treatment.

• 방사선산업학회지
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• 제17권1호
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• pp.111-118
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• 2023

The International Commission on Radiological Protection (ICRP) 103 recommends a cost-benefit analysis method as an auxiliary tool for scientific and rational decision-making for the principle of optimization of radiological protection. In order to conduct a cost-benefit analysis, the safety improvement of nuclear power by regulation must be measured and converted into monetary terms. The improvement of nuclear safety can be measured by reducing the radiation exposure dose of the people, and it is necessary to determine the coefficient to convert the radiation exposure dose into money. The monetary coefficient is calculated as the product of the statistical life value (VSL) and the nominal risk coefficient. In order to derive the monetary coefficient, the willingness to pay (WTP) can be estimated using the contingent valuation method (CVM), which quantifies the value of non-market goods by converting them into monetary units. WTP can be estimated based on the random utility model, which is the basic model for bivariate selection type conditional value measurement data. Statistical life value can be calculated using the estimated WTP and reduction in early mortality, and a monetary coefficient can be derived.

• Journal of Radiation Protection and Research
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• 제24권3호
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• pp.131-142
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• 1999

통계청에서 최근에 발표한 한국인 인구통계 자료와 미국 학술원 산하 '방사선의 생물학적 영향 위원회'의 최근 보고서(BEIR-V)의 수정 상대위험 투사모델을 적용하여 한국인의 방사선 피폭에 의한 초과 암발생 위험도를 평가하였다. 인구통계 자료로부터 유도한 사소위험도(trivial risk) 및 계산된 방사선유발 초과 암 위험도를 비교한 후 사소위험도의 수준으로 개인의 피폭선량을 유지하기 위한 국내 원전의 안전운영 목표치를 유도하였다. 방사선 피폭 유발 초과 암 위험도는 0.1 Gy의 단일피폭의 경우에는 $5.5{\times}10^{-3}$, 1.0 mGy/y로 생애연속 피폭 시엔 $3.7{\times}10^{-3}$인 것으로 평가되었다. 한국인의 모든 원인에 의한 기저사망 위험도 및 사소위험도는 각각 $5.2{\times}10^{-3}$ 및 $5.2{\times}10^{-6}$인 것으로 예상되었다. 한국인의 사소위험도 및 방사선 위험도 평가 결과로부터 유도한 국내 원전운영의 안전목표치는 대략 0.05 mSv/y로, 이 값은 미국 원자력규제위원회(USNRC)가 연방규제법 10CFR50 부록 I에서 제시하고 있는 ALARA 지침값과 거의 동일한 값으로 밝혀졌다.

• 한국방사선학회논문지
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• 제17권2호
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• pp.243-248
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• 2023

본 연구에서는 청신경초종 질환에서 방사선 수술 시 유리선량계를 이용하여 손상위험장기들의 피폭으로 인해 발생하는 2차 발암률을 분석하고자 한다. 인체 조직 등가 물질의 소아 팬텀을 사용하여, 종양의 체적은 0.506 cm³, 1.008 cm³, 2.032 cm³ 총 3개의 체적으로 설정하였고, 평균 선량은 18.4 ± 3.4 Gy로 방사선수술계획을 수립하였다. 수술 장비의 테이블에 인체 팬텀을 장착시킨 후 유리선량계를 우안, 좌안, 갑상샘, 흉선, 오른쪽 폐, 왼쪽 폐에 위치시켜 각각 피폭선량을 측정하였다. 본 연구에서 가장 큰 종양체적인 2.032 cm³의 청신경초종 질환에서 감마나이프 방사선 수술 시 손상위험장기의 피폭으로 인한 2차 암 발생률을 유리선량계로 측정한 그 결과는 10,000명 당 1.11명의 2차 암이 발생될 수 있는 것으로 계산되었다. 본 연구는 정위적 방사선 수술 시 발생할 수 있는 2차 방사선 피폭선량의 위험성을 연구하여 향후 방사선의 확률적 영향과 관련된 방사선 장해분야에 기초자료로 활용될 것이라 사료된다.

• 한국방사선학회논문지
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• 제17권3호
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• pp.459-464
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• 2023

첨단 기술의 발전으로 디지털 방사선영상 장비들이 많이 개발되어 정확한 진단과 치료에 많은 도움을 받고 있으며, 이를 안전하고 효과적으로 사용하기 위하여 전문적인 지식을 습득한 인력양성이 매우 중요하다. 진단용 X선 장비를 활용한 촬영 실습 교육에 있어서 학생들은 방사선 피폭의 위험성에 노출되어 있고, 일부 교육기관에서는 원자력안전법에 따른 관리의 어려움으로 X선 장비를 사용하지 않는 경우도 발생하고 있다. 이에 대한 해결책으로, 본 연구에서는 비전 센서와 자체 개발한 소프트웨어를 활용하여 방사선이 발생하지 않는 교육용 의료방사선 시뮬레이터를 개발하였고, 이를 통해 교육기관은 법에 따른 행정 이행 사항의 부담을 줄일 수 있고, 학생들은 방사선 피폭이 없는 건강한 실습환경에서 높은 수준의 교육 효과를 얻을 수 있게 하였다.

• 대한디지털의료영상학회논문지
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• 제12권1호
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• pp.5-8
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• 2010

Opened a court in February 10, 2006, a rule of safety management of the diagnosis radiation system was promulgated for safety of the radiation worker, patients and patients' family members. The purpose of this rule is to minimize the risk of being exposed to radiation during the process of handling X-ray. For this reason, we manufactured shielding device of mobile X-ray unit collimator for diminution of skin dose. Shielding device is made to a thickness of Pb 0.375mm. For portable chest radiography, we measured skin dose 50cm from center ray to 200cm at intervals of 20cm by Unfors Xi detector. As a result, a rule of safety management of the diagnosis radiation system has been strengthened. But there are exceptions, such as ER, OR, ICU to this rule. So shielding device could contribute to protect unnecessary radiation exposure and improve nation's health.

• 방사성폐기물학회지
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• 제21권2호
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• pp.255-269
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• 2023

Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

• Journal of Radiation Protection and Research
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• 제29권4호
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• pp.221-230
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• 2004

방사선작업종사자에게 발생한 암의 방사선 인과도를 평가하기 위한 통계적 측도로 인과확률(Probability of Causation)이 주로 이용된다. 인과확률의 계산 과정에는 다양한 형태의 불확실성이 존재하며, 따라서 인과확률은 하나의 점추정치(point estimate)가 아니라 여러 불확실성을 반영한 분포 또는 신뢰구간으로 평가되어야 한다. 본 연구에서는 국내 방사선작업종사자에게서 발생한 암의 방사선 인과도를 평가하기 위하여, 한국인의 기저자료를 반영하며 가장 최근에 발표된 NCI-CDC 모형에 근거하여 인과확률의 분포를 계산하도록 개발된 전산 프로그램 RHRI-PEPC를 소개한다. 또한 방사선작업종사자의 가상 피폭시나리오에 대한 모의실험을 통해, 인과확률의 점추정치와 불확실성 분포에 의한 방사선 인과도 평가 결과의 차이를 살펴보고 분포에 의한 평가의 경우 적절한 신뢰도 선택의 필요성을 제시한다.

• 한국안전학회지
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• 제32권1호
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• pp.134-139
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• 2017

This study has been performed to investigate the risk perceptions of employees in nuclear power plants. A representative sample of 473 employees was surveyed(about 79% response rate). The questionnaire included scales on both risk perceptions of critical five hazards that could be occurring in the nuclear power plants and two psychometric attitudes. Higher risk perceptions between managers and non-managers to five hazards used in this study were entirely obtained from the managers. It was also found that the perceived higher hazards were in the following order: radiation exposure, radioactive release, explosion, fire and radioactive waste. For the controllability, higher risk perceptions to the all factors were obtained from the managers, and higher ones were non-managers in the dread.