• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2010년도 추계학술대회 논문집
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• pp.433-438
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• 2010

Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. Nuclear Regulatory Commission Regulatory Guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement, and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors. We analyzed RVI design data of Palo Verde nuclear generating station(U.S.) and Yonggwang nuclear generating station(Korea) and investigated measuring sensors used in both of them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected the most suitable sensors for RVI CVAP in Advanced Power Reactor 1400(APR1400).

• Nuclear Engineering and Technology
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• 제36권3호
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• pp.263-275
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• 2004

For the safe management of nuclear facilities, including a radioactive waste repository, data about the facility site and the surrounding environment must be collected and managed systematically. This is particularly true for a radwaste repository, which has to be institutionally controlled for a long period after closure. The objectives of this study are (1) to establish a systematical management plan for information about a radwaste repository site and its environment, and (2) to design a database management program for this information, based on the Relative Database Management System (RDBMS). The spatial data are designed by the geodatabase, which is a new object, based on the RDBMS, to manage spatial information related to the database. To meet this requirement, a new program called 'Site Information and Total Environmental data management System (SITES)' is being developed. The scope that produced from the first step of the present study for development of the SITES is introduced. The database is designed to combine spatial and attribute data, and is designed for the establishment of the Geographic Information System (GIS). The hardware and software systems are designed with consideration given to the total data management of the items within the radioactive environment.

• 대한인간공학회:학술대회논문집
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• 대한인간공학회 1996년도 추계학술대회논문집
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• pp.125-140
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• 1996

Human Factors Engineering(HFE) program should be developed from the early stage of the design process for Nuclear Power Plant. The HFE program is conducted in accordance with the guidance in the Standard Review Plan(SRP) NUREG 0800, Chapter 18. The major purpose of this program is to reduce the incidence of human error during the operating life of the plants. A comprehensive human factors program is prepared by KOPEC to assure that key elements of human factors involvement are not inadvertently overlooked and the early, complete, and continuing inclusion of HFE in the design process. This paper is to introduce engineering steps of the HF activities to verify that the HF involvements on man-machine interface are adequate to support safe and efficient operation of nuclear power plant. If systems are developed without sufficient consideration on the HFE in the design, such systems may cost a high price due to the malfunction of the plant induced by the human errors.

• Nuclear Engineering and Technology
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• 제45권2호
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• pp.249-256
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• 2013

In accordance with the US Nuclear Regulatory Commission (US NRC), Regulatory Guide 1.20, the reactor vessel internals comprehensive vibration assessment program (RVI CVAP) has been developed for an Advanced Power Reactor 1400 (APR1400). The purpose of the RVI CVAP is to verify the structural integrity of the reactor internals to flow-induced loads prior to commercial operation. The APR1400 RVI CVAP consists of four programs (analysis, measurement, inspection, and assessment). Thoughtful preparation is essential to the measurement program, because data acquisition must be performed only once. The optimized design of a vibration and stress measurement system for the RVI CVAP is essential to verify the integrity of the APR1400 RVI. We successfully designed a vibration and stress measurement system for the APR1400 RVI CVAP based on the design materials, the hydraulic and structural analysis results, and performance tests of transducers in an extreme environment. The measurement system designed in this paper will be utilized for the APR1400 RVI CVAP as part of the first construction project in Korea.

• Nuclear Engineering and Technology
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• 제50권6호
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• pp.963-970
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• 2018

The U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 needs to perform a comprehensive vibration assessment program for reactor internals during preoperational and startup testing for nuclear power plants and extended power uprate. Although the measurement program is one of the core programs, it is rarely carried out except for a first-of-a-kind or a unique design. This article describes measurement results of vibration and stress for the comprehensive vibration assessment program for an APR-1400 reactor internals. The measurement was performed at an upper guide structure during the pre-core hot functional test of Shin Kori unit 4 reactor internals because the Shin Kori unit 3 and 4 are the first construction project for the APR-1400, and the upper guide structure assembly was to design change compared with the valid prototype. We confirmed that all measured results are within the test acceptance criteria. It means that the structural integrity of the APR-1400 reactor internals was secured for the flow-induced vibration.

• Journal of Nutrition and Health
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• 제46권2호
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• pp.156-165
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• 2013

This study examined how achievement of session goals contributes to outcomes of subjects after participation in a 12-week lifestyle intervention program in men with metabolic syndrome (MetS). Thirty office workers with MetS, aged $47.2{\pm}6.6$ years, participated in this study, from March to July, 2011. The intervention program included face-to-face counseling five times during the 12-week period. Counselors and subjects designed session goals for each round. The average of the goal achievement rate was calculated based on compliance for each round. The subjects were divided into three groups according to their tertiles of achievement rate: Low-compliance group (LC, < 59%), medium-compliance group (MC, 59-70%), and high-compliance group (HC, > 70%). Anthropometry, biochemical index, and nutrient intake were examined at baseline and at the end of the 12-week intervention program. After the intervention, diastolic blood pressure (DBP) showed a significant decrease in the LC group, and waist circumference (WC) showed a significant decrease in the MC group. Systolic blood pressure (SBP), DBP, and low-density lipoprotein cholesterol (LDL) showed a significant decrease in the HI group. Changes in SBP and DBP were significantly lower in the HC group than in the MC group (p < 0.05, p < 0.01). Changes in LDL were significantly lower in the HC group than in the MC group (p < 0.05). Results for intake of total energy, protein, fat, and sodium, as well as rates of carbohydrate and fat intake, showed a significant decrease in all participants (p < 0.05). The change in fiber was significantly higher in the HC group than in the MC group (p < 0.05). The change of fruit serving size showed a significant increase in the HC group (p < 0.01). The number of risk factors for MetS showed a significant decrease in the LC and HC groups (p < 0.05), however, no significant mean differences were observed among the three groups. In conclusion, participation in this intervention program resulted in positive effects on risk factors for MetS, nutrient intake, and dietary habits, especially in the High-compliance group.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.579-588
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• 2022

In order to meet the needs of domestic reactor severe accident analysis program, a MIDAC (Module Invessel Degraded severe accident Analysis Code) is developed and maintained by Xi'an Jiaotong University. As the accuracy of the calculation results of the analysis program is of great significance for the formulation of severe accident mitigation measures, the article select three experiments to evaluate the updated severe accident models of MIDAC. Among them, QUENCH-06 is the international standard No.45, QUENCH-16 is a test for the analysis of air oxidation, and FROMA is an out-of-pile fuel rod melting experiment recently carried out by Xi'an Jiaotong University. The heating and melting model with lumped parameter method and the steam oxidation model with Cathcart-Pawel and Volchek-Zvonarev correlations combination in MIDAC could better meet the needs of severe accident analysis. Although the influence of nitrogen still need to be further improved, the air oxidation model with NUREG still has the ability to provide guiding significance for engineering practice.

• 방사성폐기물학회지
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• 제6권2호
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• pp.147-154
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• 2008

국내 원자력발전소의 사용후핵연료 저장용량의 포화가 10년 이내에 예상되고 있으며, 소외중간저장방식을 관리 방안으로서 선정할 경우, 상당한 양의 사용후핵연료 운반이 해상 혹은 육로를 통해 매년 이루어져야만 한다. 본 논문에서는 4곳의 원자력발전소부지에 분산 저장되어 있는 사용후핵연료를 해안에 위치한 가상의 중간저장시설과 영구처분시설을 대상으로 사용후핵연료 운반물량을 효과적으로 분석할 수 있는 체계를 구축하였다. 각 발전소 부지, 중간저장시설, 영구처분시설의 저장고를 중심으로 사용후핵연료 물질 수지식을 세우고, 이에 대한 해를 VISUAL BASIC으로 구하여 운반 물량 분석이 용이하게 수행할 수 있는 컴퓨터 프로그램(CASK)을 개발하였다. 개발된 물량 분석 프로그램을 활용하여 4개 원자력 발전소 부지로부터 사용후핵연료 운반 물량을 분석하고, 운반물량 파라미터 분석을 통하여 본 프로그램의 활용도를 보였다. 개발된 사용후핵연료 운반 물량 분석 체계는 향후 운반비용 분석에도 유용하게 활용될 것이다.

• Journal of Radiation Protection and Research
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• 제45권4호
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• pp.147-153
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• 2020

Background: Malawi's 2018 National Energy Policy includes nuclear power as an energy option with an operational 100 MW targeted for 2035. Materials and Methods: This paper challenges the scope of the policy on nuclear power by reviewing its implementation strategy and comparing it to: the strategy established for coal in the same policy; some experiences from other countries; and documents by the International Atomic Energy Agency (IAEA) relating to establishing a national position on nuclear power and infrastructural requirements for a nuclear power program. Results and Discussion: It is found that the pro-nuclear position is uninformed, and targets are unrealistic owing to a lack of understanding of nature of nuclear power including the requirements for safety, security and safeguards, and nuclear infrastructure. It is apparent that neither consultation nor a proper analysis were comprehensively conducted for nuclear. Though the national energy policy suggests a national position for nuclear energy, the content does not demonstrate that the position was arrived at knowledgeably. Conclusion: Thus, nuclear power may presently be viewed as a potential energy option that is yet to be seriously considered. It is important to build an appropriate level of literacy on nuclear science and technology for policy makers, key stakeholders, and the public to be better positioned for strategizing on nuclear power.

• 한국시스템다이내믹스연구
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• 제5권2호
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• pp.125-147
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• 2004

System dynamics model has been developed and computer simulation has been peformed for the evaluation of R&D policy. One of the main results of the basecase scenario is as follows. After simulation of nuclear R&D resource allocation strategies, we discovered that their net benefit value was maximum at 130% nuclear R&D budget case. And after simulation of human resource management strategies and policy research program strategies, we confirmed that it is beneficial to allocate budgets in the early phase for human resources management program and research program for the policy.