• 공학교육연구
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• 제22권5호
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• pp.29-36
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• 2019

Here we analyze a case of redesigned course named "Prospect of Nuclear Engineering" as an example of student-entered education which came to the fore of university education innovation. This course was reformed from lecture-based to student-centered class by changing the context as follows: Stimulating students by addressing various problems or episodes behind scientific and mathematical concepts in the history; Offering experimental project to perceive the importance of differential equations; Exploring the research status and issues of nuclear engineering and the ways of attacking them by discipline; Discussing the public acceptance of nuclear power plants. Small group activities using 'small group discussion' and 'peer-learning' have been applied in this course to enhance students' critical and creative ability. In the survey, students rated highly in the fact that they could actively interact with the peers and that they could think for themselves through 'small group discussion' and 'peer-learning' which is not just the way of conveying knowledge.

• 한국융합학회논문지
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• 제8권8호
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• pp.147-154
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• 2017

본 연구는 소아핵의학검사에 사용하는 다양한 소아투여량 공식의 투여량(MBq)과 유효선량(mSv)을 산출 비교하여 적정투여량의 기준을 위한 기초자료를 제공하고자 한다. 연구는 2가지 방사성의약품($^{99m}Tc$-MDP와 $^{99m}Tc$-Pertechnetate)의 성인투여량을 기준으로 5가지 소아투여량공식(Clark법, Area법, Webster법, Young법, Solomon(Fried)법) 간 투여량과 유효선량을 비교하였다. 소아투여량 산출에 기준이 되는 성인투여량은 정준기, 이명철 '핵의학'에 수록된 값을 사용하였으며, 유효선량 산출을 위한 방사성의약품의 방사능당 유효선량(mSv/MBq)은 ICRP 80과 UNSCEAR 2008 보고서에 수록된 값을 사용하였다. 연구결과 Young법이 산출량이 가장 적으며 다른 공식과의 차이는 최소 1.7배-최대 3.4배였다. $^{99m}Tc$-MDP의 공식 간 투여량 차이는 최대 309.9MBq, 유효선량은 3.76mSv, $^{99m}Tc$-Pertechnetate는 최대 154.9MBq, 유효선량은 5.50mSv였다. 소아투여량 공식 간 투여량뿐만 아니라 유효선량도 차이가 크기 때문에 의료방사선의 최적화를 위한 적정투여량 소아산출법이 개발되어야 한다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1989년도 한국자동제어학술회의논문집; Seoul, Korea; 27-28 Oct. 1989
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• pp.795-798
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• 1989

This paper presents some results of teleoperation R&D activities for radioactive work. Heavy power manipulator feature is integrated with vision system implementation of advanced type and tool adaptation to hand gripper. Some assodiated te datth activities of interests to the teleoperation and future directions are also presented.

• 한국방사선학회논문지
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• 제16권2호
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• pp.185-194
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• 2022

국제적으로 과거 원자력 및 방사선 관련 활동으로 인해 부지 및 토양 등이 오염된 레거시 부지에 대한 해결과 관리가 관심의 대상이 되고 있다. 국내에서도 연구로 해체 등의 사례가 있었으며 북한은 최신화된 안전규제가 적용되고 있지 않을 가능성이 있으며 관련하여 운영 기록 등의 관리되지 않고 있을 가능성이 있어 레거시 부지가 될 가능성이 크다. 따라서 본 연구에서는 레거시 부지의 해결에 대한 국제 사례를 검토하고 이로부터 레거시 부지의 특성과 문제점을 파악하였다. 이에 국제 관리 기준에 따른 레거시 부지 대응 절차와 규제 체계를 분석하고 규제 체계 개발 시 고려되어야 할 사항을 도출 하였다. 레거시 부지 대응 방안의 개발은 향후 레거시 부지 발생시 대응과 레거시 부지의 발생을 예방하는데 사용될 수 있다.

• 대한인간공학회지
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• 제35권4호
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• pp.263-275
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• 2016

Objective: This paper introduces the regulatory oversight approaches and issues to consider in the course of safety culture oversight model development in the nuclear field. Common understanding on regulatory oversight and present practices of international communities are briefly reviewed. The nuclear safety culture oversight model of Korea is explained focusing on the development of safety culture definition and components, and their basic meanings. Oversight components are identified to represent the multiple human and organizational elements which can affect and reinforce elements of defense in depth system for nuclear safety. Result of validation study on safety culture components is briefly introduced too. Finally, the results of the application of the model are presented to show its effectiveness and feasibility. Background: The oversight of nuclear licensee's safety culture has been an important regulatory issue in the international community of nuclear safety regulation. Concurrent with the significant events that started to occur in the early 2000s and that had implications about safety culture of the operating organizations, it has been natural for regulators to pay attention to appropriate methods and even philosophy for intervening the licensee's safety culture. Although safety culture has been emphasized for last 30 years as a prerequisite to ensure high level of nuclear safety, it has not been of regulatory scope and has a unique dilemma between external oversight and the voluntary nature of culture. Safety culture oversight is a new regulatory challenge that needs to be approached taking into consideration of the uncontrollable aspects of cultural changes and the impacts on licensee's safety culture. Although researchers and industrial practitioners still struggle with measuring, evaluating, managing and changing safety culture, it was recognized that efforts to observe and influence licensees' safety culture should not be delayed. Method: Safety culture components which regulatory oversight will have to focus on are developed by benchmarking the concept of physical barriers and introducing the defense in depth philosophy into organizational system. Therefore, this paper begins with review of international regulatory oversight approaches and issues associated with the regulatory oversight of safety culture, followed by the development of oversight model. The validity of the model was verified by statistical analysis with the survey result obtained from survey administration to NPP employees in Korea. The developed safety culture oversight model and components were used in the "safety culture inspection" activities of the Korean regulatory body. Results: The developed safety culture model was confirmed to be valid in terms of content, construct and criterion validity. And the actual applicability in the nuclear operating organization was verified after series of pilot "safety culture inspection" activities. Conclusion: The application of the nuclear safety culture oversight model to operating organization of NPPs showed promising results for regulatory tools required for the organizations to improve their safety culture. Application: The developed oversight model and components might be used in the inspection activities and regulatory oversight of NPP operating organization's safety culture.

• 한국지능시스템학회논문지
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• 제7권1호
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• pp.34-44
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• 1997

The Belgian Nuclear Research Centre(SCK${\cdot}$CEN) has been a pioneer of the peaceful uses of nuclear energy after over forty years of existence. Recently, SCK${\cdot}$CEN's financial support of doctoral and postdoctoral research in close collaboration with universities has been a vital ingredient for securing a quality profile committed to the pursuit of execllence. FLINS, Fuzzy Logic and Intelligent technologies in Nuclear Science, was initially built within one of the postdoctoral research project at SCK${\cdot}$CEN. Among SCK${\cdot}$CEN's activities which will have an important impact on its scientific future, the application of fuzzy logic and intelligent technologies in nuclear science and engineering opens new domains in radiation protection, safety assessment, human reliability, nuclear reactor control, waste and disposal, etc. In this paper, we review the available literature on fuzzy logic in nuclear applications. We then present the initiative of R&D on fuzzy logic applications at SCK${\cdot}$CEN, namely, (1) safety control for a nuclear reactor, and (2) a safety evaluation model for nuclear transmission lines. By these two examples of nuclear applications, we illustrate the potential use of fuzzy logic in nuclear safety issues.

• 원자력산업
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• 제5권12호통권34호
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• pp.6-11
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• 1985

• Journal of Radiation Protection and Research
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• 제37권2호
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• pp.63-69
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• 2012

The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2-15 times lower than those in the PWR coolant, but the specific activities of $^{57}Co$ and $^{57}Ni$ were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.418-423
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• 2016

Background: This work was to get information about $^{90}Sr$ contamination of the environment by using soil and moss from selected areas in Jeju Island, Korea. Materials and Methods: The activities of $^{90}Sr$ in soil and moss samples were investigated at nine locations of Jeju island, Korea. The soil samples have been collected at 4 sites of Jeju island during June to August of 2013, analyzed for vertical distribution of $^{90}Sr$ activities. The moss samples have been collected at 5 sites of Jeju island during November of 2011 to June of 2012, and analyzed for radioactive $^{90}Sr$. Results and Discussion: The $^{90}Sr$ vertical concentrations in the investigated soil samples were 2.77 to $18.24Bq{\cdot}kg^{-1}$ in eastern part, 1.69 to $18.27Bq{\cdot}kg^{-1}$ in northern part, 3.76 to $13.46Bq{\cdot}kg^{-1}$ in the western part and 1.09 to $8.70Bq{\cdot}kg^{-1}$ in the southern part of the Mt. Halla in Jeju island, respectively. Activities of $^{90}Sr$ show the highest value at the surface soil and decrease with depth. The activity concentration measured was in the range of 79.6 to $363Bq{\cdot}kg^{-1}$ -dry moss. Conclusion: This material is expected to be basis reference for survey of environmental radioactivity in Jeju Island.

• 대한핵의학회지
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• 제10권1호
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• pp.55-60
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• 1976

Marked augmentation of urinary aldosterone excretion following furosemide administration was observed in previous experiment. In this study, author measured the changes of aldosterone secretion after furosemide administration in normotensive young volunteers with high sodium intake. After intravenous injection of $1.2-^3H-aldosterone$, urine samples were collected in course of time until 24 hours after the injection. Furosemide administration was done at 30 minutes prior to aldosterone injection. Specific activities of $^3H-aldosterone$ during and after diuresis were measured and aldosterone secretion rates were calculated dividing the doses by specific activities. Results were as followed 1. Furosemide resulted in a marked increase in urinary aldosterone excretion. 2. Furosemide lead to an increase in both sodium and potassium excretion. 3. Aldosterone secretion rate was also increased during furosemide diuresis, but the rate was smaller than that of urinary excretion. 4. Continuous modest increase in aldosterone secretion rate was shown after diuresis and total excess amount of aldosterone secretion for 24 hrs was equivalent to the amount of aldosterone excretion produced by diruesis. 5. Abrupt marked loss of circulating aldosterone produced by diuresis was supplemented by long lasting increase in secretion for over twenty four hours.