• 자원ㆍ환경경제연구
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• 제22권2호
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• pp.367-391
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• 2013

후쿠시마원자력발전소의 사고를 계기로 원전의 안전대책비용, 사고위험대응비용과 같은 외부비용들의 존재가 부각되고 있다. 이에 본 연구는 원전의 외부비용들 중에서 추가안전대책비용과 사고위험대응비용을 추정하고, 이를 발전원가 및 전기요금에 반영하여 변화정도를 살폈다. 원전의 추가안전대책비용은 70~90%의 이용률에서 0.53원/kWh~0.80원/kWh으로 원전의 발전원가에 큰 영향을 미치지는 않는다. 사고위험대응비용은 원전사고피해규모별, 사고발생빈도별, 이용률별로 0.0025원/kWh~26.4188원/kWh로 추정되었다. 사고위험대응비용을 포함시키면 원전발전원가는 47.58원/kWh~85.92원/kWh가 된다. 2011년을 기준으로 사고위험대응비용을 내부화한 경우의 전기요금의 증가율은 70~90%의 이용률에서 0.001%~10.0563% 로 추정되었다. 본 연구는 원전의 외부비용을 내부화하는 방법으로서 외부비용을 발전원가에 포함하여 전기요금에 반영하였다. 본 연구는 지금까지 우리나라에 논의되지 않았던 원전 외부비용을 내부화하는 방법의 하나가 될 것이다.

• Journal of Welding and Joining
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• 제29권2호
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• pp.56-63
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• 2011

his paper aimed to understand the residual stress in the dissimilar metal welds of nuclear power plant. Two kinds of residual stress were considered, which caused by welding and machining. Residual stress due to mechanical machining was measured by hole-drilling technique and x-ray diffraction method for the SA508 and F316L. Weld residual stress at dissimilar metal weld between SA508 and F316L was evaluated by FEA. Residual stress profiles were obtained for the inside surface and through thickness of welds. Machining effect was also analyzed by FEA. According to the residual stress measurement, it was observed that mechanical machining can generate tensile stress on the surface of the test material. However, FEA results showed that mechanical machining did not increase the tensile stress on the surface of weld region. Further study with more elaborate measurement and numerical analysis is required to identify the effect of machining on residual stress in the dissimilar metal weld region.

• 자원ㆍ환경경제연구
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• 제25권3호
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• pp.449-470
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• 2016

본 연구는 14개 원전 운영국, 22개 제조업군을 대상으로 전원에서 원전이 차치하는 비중의 변화가 제조업 성장에 미치는 영향을 분석하였다. 한 국가의 원전비중 변화는 전력가격의 변화를 통하여 산업의 부가가치와 생산량에 영향을 미친다는 가설을 동태적 패널데이타 모형을 이용하여 분석하였다. 주요 6개국의 분석결과에 따르면 원전비중이 1%p 증가할 경우 전기 가격은 0.8%감소하는 것으로 추정이 되었다. 또한 주요 6개국에 국한된 분석 결과에서는 원전 비중이 1%p 증가하였을 경우 산업별 부가가치 및 생산량은 단기에 0.16% 및 0.23% 증가하였고 장기적인 효과는 0.51% 및 0.85%에 달하였다. 전력요금 절감을 통하여 원전이 산업경쟁력에 기여하는 효과는 전력시장의 제도에 따라 달리하는 것으로 추정이 된다. 영국과 일본과 같이 전력가격 수준이 높고 변동폭이 큰 국가에서 전력요금 절감을 통한 산업경쟁력 제고가 크게 나타나는 반면, 원전 축소정책을 지향하는 독일에서는 전력요금 절감보다는 안정적인 전력수급을 통하여 산업경쟁력에 기여하는 것으로 본 논문의 결과를 해석할 수 있다.

• Journal of Radiation Protection and Research
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• 제39권2호
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• pp.118-126
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• 2014

향후 여론의 주도층이 될 일부 초, 중, 고등학생을 대상으로 방사선이용 분야 중 일반적으로 사회적 수용성이 절실히 필요한 방사선조사식품, 원자력발전, 의료방사선에 대한 인식, 지식 및 태도를 설문 조사한 결과 사회적 수용성 증진을 위한 교육적 근거가 일부 도출되었다. 첫째, 여학생 중심의 수업과 남학생 중심의 수업설계에 차별화된 전략이 필요하다. 여학생 보다 남학생이 방사선조사식품의 객관적 지식수준(p<0.039), 원자력발전의 필요성(p<0.001) 및 객관적 지식(p<0.001), 우리나라 원자력발전소 건설 찬성태도 (p<0.000), 의료방사선의 필요성(p<0.001) 및 객관적 지식(p<0.001), 의료방사선 이용 태도(p<0.007, p<0.001)가 모두 높기 때문이다. 둘째, 원자력발전의 필요성, 안전성에 대한 국민 이해를 돕기 위한 설명에서는 의료방사선의 필요성과 안전성에 대한 정보를 함께 제공하는 것이 교육효과를 높일 수 있다. 남, 여학생 모두 의료방사선이 가장 필요하며(p<0.001), 의료방사선이 가장 안전하며(p<0.001), 원자력 발전이 가장 안전하지 않다고(p<0.013) 인식하고 있다. 또한 의료방사선과 원자력 발전의 상관관계가 가장 높게 나타났기 때문이다. 셋째, 초, 중, 고등학생이 방사선이용 분야별로 인식의 패턴이 다르므로 학급별로 차별화된 강의내용이 필요하다. 초등학생은 원자력발전에 대한 교육흥미도가 높고(p<0.005), 방사선조사식품이 안전하다고 인식하고 있으며(p<0.001), 방사선조사식품을 섭취하겠다는 태도가 가장 높았다(p<0.001). 중학생은 의료방사선에 대한 교육흥미도가 높고(p<0.018), 원자력발전(p<0.001)과 의료방사선(p<0.002)에 대해 안전하다고 인식하고 있으며, 치료 방사선이용 태도가 가장 높았다(p<0.001). 고등학생은 원자력발전(p<0.001)과 의료방사선(p<0.001)에 대한 객관적 지식수준이 가장 높고, 의료방사선이 가장 필요하다고 인식하고 있으나(p<0.017), 원자력발전이 가장 안전하지 않다고 인식하고 있다(p<0.001). 방사선조사식품 섭취 태도(p<0.001), 거주지에 원자력발전 건설을 찬성하는 태도(p<0.001) 모두 낮았다. 넷째, 객관적 지식 중심의 교육제공보다 인식변화 및 태도증진을 위한 교육프로그램이 제공되어야 한다. 객관적 지식과 방사선조사식품의 필요성, 객관적 지식과 원자력발전에 대한 안전성 및 교육흥미도, 객관적 지식과 의료방사선의 교육흥미도 및 정보습득에는 상관관계가 없었다. 특히, 고등학생의 경우 객관적 지식수준은 가장 높았으나 거주지의 원자력발전 건설에 대해 찬성하는 태도와 방사선조사식품 섭취태도가 가장 낮았기 때문이다. 국내에서 원자력 및 방사선이용에 대한 사회적 수용성을 향상시키기 위해 필요성과 안전성에 대한 인식과 지식 및 태도 향상에 관한 교육프로그램을 전략적으로 제공하는 것이 바람직하다.

• 한국태양광발전학회지
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• 제4권2호
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• pp.45-53
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• 2018

Natural gas demand for power generation continued to increase until 2013 due to the expansion of large-scale LNG power plants after the black-out of 2011. However, natural gas demand for power generation has decreased sharply due to the increase of nuclear power and coal power generation. But demand for power generation has increased again as energy policies have changed, such as reducing nuclear power and coal power plants, and abnormal high temperatures and cold waves have occurred. If the gas pipeline pressure can be properly maintained by predicting these fluctuations, it can contribute to enhancement of operation efficiency by minimizing the operation time of facilities required for production and supply. In this study, we have developed a regression model with daily power demand and base power generation capacity as explanatory variables considering characteristics by day of week. The model was constructed using data from January 2013 to December 2016, and it was confirmed that the error rate was 4.12% and the error rate in the 90th percentile was below 8.85%.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1369-1377
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• 2021

Nowadays, it is necessary to accelerate the construction of new power plant in face of rising energy demand in such a way that the electricity will be generated at the lowest cost while reducing emissions caused by that generation. The expansion planning is one of the most important issues in electricity management. Nuclear energy comes forward with the low-carbon technology and increasing competitiveness to expand the share of generated energy by introducing Gen IV reactors. In this paper, the generation expansion planning of these new Gen reactors is investigated using the WASP software. Iran power grid is selected as a case of study. We present a comparison of the twenty-one year perspective on the future with the development of (1) traditional thermal power plants and Gen II reactors, (2) Gen III + reactors with traditional thermal power plants, (3) Gen IV reactors and traditional thermal power plants, (4) Gen III + reactors and the new generation of the thermal power plant, (5) the new generation of thermal power plants and the Gen IV reactors. The results show that the Gen IV reactors have the most developing among other types of power plants leading to reduce the operating costs and emissions. The obtained results show that the use of new Gen of combined cycle power plant and Gen IV reactors make the emissions and cost to be reduced to 16% and 72% of Gen II NPPs and traditional thermal power plants, respectively.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2888-2898
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• 2021

Vital area identification (VAI) is an essential procedure for the design of physical protection systems (PPSs) for nuclear power plants (NPPs). The purpose of PPS design is to protect vital areas. VAI has been improved continuously to overcome the shortcomings of previous VAI generations. In first-generation VAI, a sabotage fault tree was developed directly without reusing probabilistic safety assessment (PSA) results or information. In second-generation VAI, VAI model was constructed from all PSA event trees and fault trees. While in third-generation VAI, it was developed from the simplified PSA event trees and fault trees. While VAIs have been performed for NPPs in full-power operations, VAI for NPPs in low-power and shutdown (LPSD) operations has not been studied and performed, even though NPPs in LPSD operations are very vulnerable to sabotage due to the very crowded nature of NPP maintenance. This study is the first to research and apply VAI to LPSD operation of NPP. Here, the third-generation VAI method for full-power operation of NPP was adapted to the VAI of LPSD operation. In this study, LPSD VAI for a few plant operational states (POSs) was performed. Furthermore, the operation strategy of vital areas for both full-power and LPSD operations was discussed. The LPSD VAI method discussed in this paper can be easily applied to all POSs. The method and insights in this study can be important for future LPSD VAI that reflects various LPSD operational states. Regulatory bodies and electric utilities can take advantage of this LPSD VAI method.

• Journal of Radiation Protection and Research
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• 제42권4호
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• pp.222-228
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• 2017

Background: On June 18, 2017, Korea's first commercial nuclear reactor, the Kori Nuclear Power Plant No. 1, was permanently suspended, and the capacity of nuclear power generation facilities will be adjusted according to the governments denuclearization policy. In these circumstances, it is necessary to assess the quality of radiation safety management in nuclear power plants in Korea by evaluating the radiation dose associated with them. Materials and Methods: The average annual radiation dose per unit, the annual radiation dose per person, and the annual dose distribution were analyzed using the radiation dose database of nuclear reactors for the last 5 years. The results of our analysis were compared to the specifications of the Nuclear Safety Act and Medical Law in Korea. Results and Discussion: The annual average per unit radiation dose of global major nuclear power generation was 720 man-mSv, while that of Korea's nuclear power plants was 374 manmSv. No workers exceeded 50 mSv per year or 100 mSv in 5 years. The individual radiation dose according to occupational exposure was 0.59 mSv for nuclear workers, 1.77 mSv for non-destructive workers, and 0.8 mSv for diagnostic radiologists. Conclusion: The radiation safety management of nuclear power plants in Korea has achieved the best outcomes worldwide, which is considered to be the result of the as-low-as-reasonably-achievable (ALARA) approach and strict radiation safety management. Moreover, the occupational exposures were also very low.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2208-2219
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• 2024

Kylin-2 is an advanced neutronics lattice code, developed by Nuclear Power Institute of China. High-precision multigroup cross section library is need for KYLIN-2 to carry out simulation of current pressurized water reactor (PWR) and advanced reactor. In this paper a multigroup cross section library generation system named TPAMS was developed, the methods in TPAMS dealing with resonance data such as subgroup parameters, lambda factor, resonance integral were discussed. Moreover, the depletion chain simplification method was studied. TPAMS can produce multigroup library in binary and ASIIC formats, including detailed data contents for resonance, transport and depletion calculations. A multigroup cross section library has been generated for KYLIN-2 based on TPAMS system. The multigroup cross section library was verified through the analysis of various criticality and burnup benchmarks, the values of multiplication factor and isotope density were compared with the experiment data. Numerical results demonstrate the accuracy of the multigroup cross section library and the reliability of the multigroup cross section library generation system TPAMS.

• 대한산업공학회지
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• 제39권3호
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• pp.183-191
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• 2013

We address the power generation mix problem that considers not only nuclear and fossil fuels such as oil, coal and LNG but also renewable energy technologies. Unlike nuclear or other generation technologies, the expansion plan of renewable energy is highly uncertain because of its dependency on the government policy and uncertainty associated with technology improvements. To address this issue, we conduct a delphi survey and forecast the capacity of renewable energy. We further propose a stochastic mixed integer programming model that determines an optimal capacity expansion and the amount of power generation using each generation technology. Using the proposed model, we test eight generation mix scenarios and particularly evaluate how much the expansion of renewable energy contributes to the total costs for power generation in Korea. The evaluation results show that the use of renewable energy incurs additional costs.