• Journal of Radiation Protection and Research
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• 제29권1호
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• pp.65-71
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• 2004

원자력 시설의 사고시 환경으로 방출된 방사성물질로부터 초기 주민의 피해 최소화를 위한 대응행위 결정지원 방안으로 다속성 효용분석 법이 고찰되었다. 속성의 효용함수는 비선형 2차 함수로 가정하였으며, 속성의 가중계수는 swing weighting 방법을 사용하여 결정하였다. 본 연구는 원자력시설의 사고시 초기 대응행위 결정지원을 위한 다속성 효용분석법의 적용성에 한정하며, 스트레스 등과 같은 비정량적 속성은 아직까지 자료의 부족으로 포함하지 않았다. 가상사고 시나리오를 구성하여 무대응, 대피, 소개에 대해 속성 값의 변화에 따른 행위에 대한 총 효응 값을 고찰하였다. 적용한 결과, 피폭선량과 선량의 금전가의 변화에 따라 행위의 총 효용 값은 뚜렷이 다르게 나타났다. 피폭선량과 선량의 금전가의 증가에 따라 대피보다 사회적 영향 등 여러 측면에서 보다 극단적인 대응행위인 소개의 총 효용 값의 순위는 뚜렷이 증가한 반면, 무 대응의 순위는 감소하였다. 선량의 기대 확률도 대응행위 결정지원에 있어서 중요한 변수로 나타났는데, 상대적으로 고선량의 기대 확률이 높을수록 행위의 우선 순위가 바뀌는 교차점에서 선량의 금전가는 보다 낮게 나타냈다. 또한 선량에 대한 회피심리가 강하게 적응할수록 행위의 우선 순위가 바뀌는 선량의 교차점은 보다 낮게 나타났다.

• Journal of Radiation Protection and Research
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• 제27권1호
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• pp.21-26
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• 2002

원자력 사고로 인해 방사성물질이 환경으로 방출되는 기간동안 강우가 있을 경우 음식물의 오염 영향을 고려하기 위해 개발된 역동학적 섭식경로모델을 개선하였다. 이를 위해 핵종별 강우량에 따른 농작물에 대한 습차단 상수를 유도하였으며, 아울러 개발된 역동학적 섭식경로모델에 대한 수학적 모델을 재정립하였다. 평가결과, 같은 지표위 농도에 대해 강우는 음식물의 오염을 크게 감소시키며 강우량 증가에 따라 오염은 급격히 감소하였다. 이러한 사실은 원자력 사고 기간동아 강우가 있을 경우 농작물의 건차단 만을 고려한 기존 역동학적 섭식경로모델을 사용하여 평가하였을 때 그 결과는 과대 평가될 수 있다는 사실을 나타낸다. 본 연구에서 고려하는 핵종 ($^{137}Cs,\;^{90}Sr,\;^{131}I$) 중에서 강우량에 따른 음식물의 농도 감소는 $^{131}I$에서 가장 뚜렷하게 나타났으며, $^{90}Sr$이 가장 영향이 적었다.

• 대한소아치과학회지
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• 제36권4호
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• pp.607-612
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• 2009

소아기의 악성 종양은 질병으로 인한 소아 사망의 가장 흔한 원인이다. 이에 대한 대표적인 치료 방법으로 항암 화학 요법과 방사선 요법의 단독 사용 혹은 이들의 병용을 들 수 있다. 그러나 이러한 치료 방법은 다양한 구강 내 합병증을 동반한다. 성인과 달리 소아 환자는 항암치료 시기에 일부 영구치가 활발한 발육단계에 있으므로 발육중인 치아에 치과적 합병증이 예상된다. 치과적 합병증의 정도는 화학약물의 종류, 용량 및 방사선 조사 빈도와 치료 당시 환자의 나이에 따라 달라진다. 본 증례들에서는 특정 영구치의 발육단계에 있는 만 1-4세경에 종양의 치료를 위해 항암 화학 요법과 방사선 치료를 받은 어린이 3명을 대상으로 치료 내용과 치아 발육 상황을 검토해 보았다. 이환된 치아의 수나 그 정도에 차이는 있으나, 각각의 환자에서 영구치 치배의 선천 결손, 왜소치, 치근 저형성 등 발육장애 관련 소견이 관찰되었다. 항암치료를 받은 병력이 있는 소아에 있어서 항암치료 이후에 나타날 수 있는 일반적인 구강 합병증 이외에 발육시기 동안 치아에 미치는 영향을 고려하여, 공간 문제를 포함하여 향후 발생 할 수 있는 다앙한 문제점 예방을 위한 장기적인 관찰과 관리가 필요할 것으로 생각된다.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.101-107
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• 2020

Background: An important lesson learned from the Fukushima accident is that the transition to the mid- and long-term phases from the emergency-response phase requires less than a year, which is not very long. It is necessary to know how much radioactive material has been deposited in an urban area to establish mid- and long-term countermeasures after a radioactive accident. Therefore, an urban deposition model that can indicate the site-specific characteristics must be developed. Materials and Methods: In this study, the generalized urban deposition velocity and the subsequent variation in radionuclide contamination were estimated based on the characteristics of the Korean urban environment. Furthermore, the application of the obtained generalized deposition velocity in a hypothetical scenario was investigated. Results and Discussion: The generalized deposition velocities of ¹³⁷Cs, ¹⁰⁶Ru, and ¹³¹I for each residence type were obtained using three-dimensional (3D) modeling. For all residence types, the deposition velocities of ¹³¹I are greater than those of ¹⁰⁶Ru and ¹³⁷Cs. In addition, we calculated the generalized deposition velocities for each residential types. Iodine was the most deposited nuclide during initial deposition. However, the concentration of iodine in urban environment drastically decreases owing to its relatively shorter half-life than ¹⁰⁶Ru and ¹³⁷Cs. Furthermore, the amount of radioactive material deposited in nonresidential areas, especially in parks and schools, is more than that deposited in residential areas. Conclusion: In this study, the generalized urban deposition velocities and the subsequent deposition changes were estimated for the Korean urban environment. The 3D modeling was performed for each type of urban residential area, and the average deposition velocity was obtained and applied to a hypothetical accident. Based on the estimated deposition velocities, the decision-making systems can be improved for responding to radioactive contamination in urban areas. Furthermore, this study can be useful to predict the radiological dose in case of large-scale urban contamination and can support decision-making for long-term measurement after nuclear accident.

• 수산경영론집
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• 제50권2호
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• pp.23-40
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• 2019

The main purpose of this study is to analyze and examine the problems of the law systems of the safety and maintenance of nuclear facilities and to propose the improvements with respect to the related problems especialy focused on safety management of aquatic products. Therefore, the results of the paper would be helpful to build an effective management law system of safety and maintenance of nuclear facilities and fisheries products. The research methods are longitudinal and horizontal studies. This study compares domestic policies with foreign policies of nuclear plants and aquatic products. Using the above methods, examining the current system of nuclear-related laws and regulations, we have found that there exist 13 Acts including "Nuclear Safety Act", etc. Safety laws related on nuclear facilities have seven Acts including "Nuclear Safety Act", "the Act on Physical Protection and Radiological Emergency", "Radioactive waste control Act", "Act on Protective Action Guidelines against Radiation in the Natural Environment", "Special Act on Assistance to the locations of facilities for disposal low and intermediate level radioactive waste", "Korea Institute of Nuclear Safety Act". "Act on Establishment and Operation of the Nuclear Safety and Security Commission". The seven laws are composed of 119 legislations. They have 112 lower statute of eight Presidential Decrees, six Primeministrial Decrees and Ministrial Decrees, 92 administrative rules (orders), 6 legislations of local self-government aself-governing body. The concluded proposals of this paper are as follows. Firstly, we propose that the relationship between the special law and general law should be re-established. Secondly, the terms with respect to law system of safety and maintenance of nuclear plants should be redefined and specified. Thirdly, it is advisable to re-examine and re-establish the Law System for Safety and Maintenance of Nuclear Facilities. and environmental rights like the French Nuclear Safety Legislation. Lastly, inadequate legislation on the aquatic pollution damage should be re-established. It is necessary to ensure sufficient transparency as well as environmental considerations in the policy decisions of the Korean government and legislation of the National Assembly. It is necessary to further study the possibilities of accepting the implications of the French legal system as a legal system in Korea. In conclusion, the safety management of nuclear facilities is not only focused on the secondary industry and the tertiary industry centering on power generation and supply, but also on the primary industry, which is the food of the people. It is necessary to prevent damage to be foreseen. Therefore, it is judged that there should be no harm to the people caused by contaminated marine products even if the "Food Safety Law for Prevention of Radiation Pollution Damage" is enacted.

• 한국안전학회지
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• 제35권1호
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• pp.116-129
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• 2020

Resilience is defined as the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations or functions with the related systems under both expected and unexpected conditions. Resilience engineering is a relatively new paradigm for safety management that focuses on how to cope with complexity under pressure or disturbance to achieve successful functioning. This study aims to develop a quantitative resilience model for severe accident response organizations of nuclear power plants using the Analytic Hierarchy Process (AHP) method. First, we investigated severe accident response organizations based on a radiation emergency plan in the Korean case and developed a qualitative resilience model for the organizations with resilience-influencing factors, which have been identified in the author's previous studies. Then, a quantitative model for entire severe accident response organizations was developed by using the Analytic Hierarchy Process (AHP) method with a tool for System Dynamics. For applying the AHP method, several experts who are working on implementing, regulating or researching the severe accident response participated in collecting their expertise on the relative importance between all the possible relations in the model. Finally, a sensitivity analysis was carried out to discuss which factors have the most influenceable on resilience.

• 한국전기전자재료학회논문지
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• 제29권8호
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• pp.483-488
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• 2016

Ultrasound imaging by using piezoelectric materials, such as lead zirconium titanate (PZT) has been one of the most preferred modes of imaging in the medical field due to its simple, low cost and non-ionizing radiation in comparison to other imaging techniques. Recently, the market demand for portable ultrasound is becoming larger with applications in developing countries, disaster area, military, and emergency purposes. However, most of ultrasound probes used is bulky and high power consumable, so unsuitable for such applications. In this study, the 3 layered ceramic specimen consisted of 128 pitches of $420{\mu}m$ in width and $450{\mu}m$ in thickness were prepared by using the Ti-rich PZT compositions co-fired at $1,050^{\circ}C$. Their electrical and ultrasound pulse-echo properties were investigated and compared to the single layer specimen. The 3 layered ultrasound probe showed 1.584 V of Vp-p, which is 3.2 times higher than single layered one, implying that it would allow effectively such a portable ultrasound probe system. The result were discussed in terms of higher capacitance, lower impedance and higher dielectric coefficient of the 3 layered ultrasound probe.

• Nuclear Engineering and Technology
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• 제48권1호
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• pp.16-25
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• 2016

In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconiumalloy fuel claddingmaterials are rapidlyheateddue to nuclear decay heating and rapid exothermic oxidation of zirconium with steam. This heating causes the cladding to rapidly react with steam, lose strength, burst or collapse, and generate large quantities of hydrogen gas. Although maintaining core cooling remains the highest priority in accident management, an accident tolerant fuel (ATF) design may extend coping and recovery time for operators to restore emergency power, and cooling, and achieve safe shutdown. An ATF is required to possess high resistance to steam oxidation to reduce hydrogen generation and sufficient mechanical strength to maintain fuel rod integrity and core coolability. The initiative undertaken by Electric Power Research Institute (EPRI) is to demonstrate the feasibility of developing an ATF cladding with capability to maintain its integrity in $1,200-1,500^{\circ}C$ steam for at least 24 hours. This ATF cladding utilizes thin-walled Mo-alloys coated with oxidation-resistant surface layers. The basic design consists of a thin-walled Mo alloy structural tube with a metallurgically bonded, oxidation-resistant outer layer. Two options are being investigated: a commercially available iron, chromium, and aluminum alloy with excellent high temperature oxidation resistance, and a Zr alloy with demonstratedcorrosionresistance.Asthese composite claddings will incorporate either no Zr, or thin Zr outer layers, hydrogen generation under severe LOCA conditions will be greatly reduced. Key technical challenges and uncertainties specific to Moalloy fuel cladding include: economic core design, industrial scale fabricability, radiation embrittlement, and corrosion and oxidation resistance during normal operation, transients, and severe accidents. Progress in each aspect has been made and key results are discussed in this document. In addition to assisting plants in meeting Light Water Reactor (LWR) challenges, accident-tolerant Mo-based cladding technologies are expected to be applicable for use in high-temperature helium and molten salt reactor designs, as well as nonnuclear high temperature applications.

• 한국화재소방학회논문지
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• 제32권6호
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• pp.141-149
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• 2018

원전 관할 소방관의 위험인식은 업무 수행과 관련을 가지며, 재난대응의 준비 현황을 반영하기 때문에 체계적인 이해가 필요하다. 이에 본 연구는 원전 관할 소방관들의 고유한 위험인식의 구조와 내용을 개념도 방법으로 연구하였다. 원전 관할 소방관 18명이 아이디어 산출 단계에서 참여하였고, 원전 관할 소방관 15명이 진술문 구조화 단계에 참가하였다. 분석 결과, 원전 화재 대응에 대한 소방관들의 위험인식은 '두려움과 통제'와 '대응 자원' 두 차원을 중심으로 구조화되었다. 피폭에 대한 두려움과 낮은 통제, 통제와 권한 부족에 따른 불안, 공조와 신뢰의 부족, 권한제약 및 인력부족, 장비, 매뉴얼, 정보의 미비, 지식과 교육의 부족의 6개 범주가 위험인식의 주요 내용으로 도출되었다. 원전 화재에 대한 재난적 결과 기대와 대응자원의 부족에 따른 낮은 통제감이 위험인식을 높이는 주요 요소들로 확인되었다. 소방관들의 위험인식이 지니는 주요 특징들, 대응 역량과 대응자원을 포괄하는 복잡한 지식구조와 두려움과 신뢰 간의 밀접한 관련성 등에 관해 논의하였다.

• 한국안전학회지
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• 제33권6호
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• pp.144-156
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• 2018

Level 3 Probabilistic Safety Assessment (PSA) is performed for the risk assessment that calculates radioactive material dispersion to the environment. This risk assessment is performed with a tool of MELCOR Accident Consequence Code System (MACCS2 or WinMACCS). For the off-site consequence analysis of multi-unit nuclear power plant (NPP) accident, the single location (Center Of Mass, COM) method has been usually adopted with the assumption that all the NPPs in the nuclear site are located at the same COM point. It was well known that this COM calculation can lead to underestimated or overestimated radionuclide concentration. In order to overcome this underestimation or overestimation of radionuclide concentrations in the COM method, Multiple Location (ML) method was developed in this study. The radionuclide concentrations for the individual NPPs are separately calculated, and they are summed at every location in the nuclear site by the post-processing of radionuclide concentrations that is based on two-dimensional Gaussian Plume equations. In order to demonstrate the efficiency of the ML method, radionuclide concentrations were calculated for the six-unit NPP site, radionuclide concentrations of the ML method were compared with those by COM method. This comparison was performed for conditions of constant weather, yearly weather in Korea, and four seasons, and the results were discussed. This new ML method (1) improves accuracy of radionuclide concentrations when multi-unit NPP accident occurs, (2) calculates realistic atmospheric dispersion of radionuclides under various weather conditions, and finally (3) supports off-site emergency plan optimization. It is recommended that this new method be applied to the risk assessment of multi-unit NPP accident. This new method drastically improves the accuracy of radionuclide concentrations at the locations adjacent to or very close to NPPs. This ML method has a great strength over the COM method when people live near nuclear site, since it provides accurate radionuclide concentrations or radiation doses.