• Title/Summary/Keyword: Kori-1 nuclear power plant

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Perception Survey of Nuclear Power after the Nuclear Plant and Thyroid Cancer Controversy (원자력발전소와 갑상선암 논란 이후 원자력에 대한 인식 조사)

  • Lee, Jae-Heon;Park, Eun-tae
    • Journal of the Korean Society of Radiology
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    • v.11 no.1
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    • pp.19-25
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    • 2017
  • In this study, in order to analyze the general awareness of the nuclear power according to the controversy of thyroid cancer around nuclear plant, we investigated risks, preference and economics regarding type of power, and awareness of pre-post nucl ear power targeting the Busan Metropolitan residents. As a result, there has been a change in people's awareness of nuclear power as a result of the controversy thyroid cancer around nuclear plant. Especially, there was the greatest increase in the risk factors compared to before the event(p<0.05). Negative awareness of nuclear risk was shown to be expressed differently accor ding to the difference between groups. It is thought that this is due to the different prior experience of each individuals or obtained information through the interaction with others rather than on scientific and objective grounds. In order to establish a nuclear power policy considering the level of the people in the future, it seems that the efforts to understand the attitudes and opinions of people about nuclear power and above all, a scientific trust in nuclear power should be guaranteed.

Comparison between ISO 9000 Specification and Nuclear Quality Assurance Specification and Expected Application Effect (ISO 9000규격과 원자력품질보증 규격과의 비교 및 예상 적용 효과)

  • Lee, Tae-Hoon;Ha, Ji-Hoon
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.34 no.3
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    • pp.79-89
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    • 2011
  • Since commercial operation of Kori-1 nuclear power plant in 1978, twenty units are under operation and six units are under construction at 2011 present. Nuclear power become a main energy source in our country. However, the plant was constructed by a USA vendor in its beginning period, the Quality Assurance requirements of USA was applied. Even though Quality Assurance requirements were newly established to the Korea Atomic Energy Act, its contents are quite similar to those of USA. And 10 CFR 50 App.B, ASME NQA-1 apply to most of nuclear industries as a quality assurance plan. In this paper, Quality Assurance requirement of domestic nuclear industries has been investigated and applicable method of ISO Quality Assurance application to the nuclear industries is suggested by a comparison ISO 9000 and nuclear quality assurance specification.

Radiation Exposure from Nuclear Power Plants in Korea: 2011-2015

  • Lim, Young Khi
    • Journal of Radiation Protection and Research
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    • v.42 no.4
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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.

Plan of BIM-based Quantity Take-off for Nuclear Power Plant Decommissioning (BIM을 활용한 원전 해체 물량산출 방안)

  • Jung, In-Su;Won, Ji-Sun
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.16 no.9
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    • pp.6297-6304
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    • 2015
  • Nuclear power plant decommissioning has attracted attention according to the shutdown decision of Kori 1 which is Korea's first nuclear power plant. Nuclear power plant decommissioning is the one who never experienced ever in our country. So, its process is difficult and time-consuming. In addition, it is difficult to determine the decommissioning quantity. This study proposed the plan that can be used in quantity take-off for nuclear power plant decommissioning using BIM technology being utilized in recent construction industry. As a result, we suggested the method of BIM-based quantity take-off such as the selection decommissioning method and process, setting up of BIM modeling environment, establishment of OBS & WBS, integrated BIM modeling, the definition of quantity property. The proposed plan can be utilized usefully from when permanent stopping nuclear power plant occurs intensively. Furthermore, the overseas nuclear power plant decommissioning project order also are expected through technology securement based on this plan.

Groundwater Flow and Tritium Transport Modeling at Kori Nuclear Power Plant 1 Site (고리 1발전소 부지 내 지하수 유동 및 삼중수소 이동 모델링)

  • Sohn, Wook;Sohn, Soon-Hwan;Chon, Chul-Min;Kim, Kue-Yong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.9 no.3
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    • pp.149-159
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    • 2011
  • Nuclear power utilities should establish a site-specific groundwater monitoring program for early detection of unplanned radioactive material's releases which can occur due to degradation of systems, structures and components of the nuclear power plants in order to keep the impact of the unplanned releases on the environment and the residents as low as reasonably achievable. For this end, groundwater flow on site should be evaluated based on characterization of the hydrogeology of a site of concern. This paper aims to provide data necessary for establishing groundwater monitoring program which is currently considered at Kori nuclear power plant 1 by characterizing groundwater flow system on the site based on the existing hydrogeological studies and related documents, and by modeling tritium transport. The results showed that the major groundwater flow direction was south-west and that most of groundwater entered a southern and eastern seas. Although the tritium plume also released into the sea, its rate was delayed by dewatering sump.

Radioactivity Calculation Considering Kori Unit 1 Operation History for the Defected Baffle Former Bolts (고리1호기 가동이력을 고려한 손상 배플포머볼트 방사화 계산)

  • Young Jae Maeng;Hyun Chul Lee;Myeong Ho Lee;Seong Sik Hwang;Seung Jin Oh;Yun Suk Jang
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.19 no.1
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    • pp.20-26
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    • 2023
  • The defected baffle former bolts of Kori unit 1 were withdrawn to analyze the cause of damage and gamma-ray measurement is being scheduled. Prior to that, in order to calculate the specific radioactivity value of the baffle former bolt, a radioactivity calculation method considering the actual operation history of the nuclear power plant is introduced and the calculation results are shown. In particular, the radioactivity calculation method considering the operation history is obtained by defining the monthly contribution factor from the actual monthly operation history. As a result, the results considering operation history are 16-28% lower than the general radioactivity calculation results. These results can contribute to establish a reasonable but economical strategy when planning nuclear power plant decommissioning.

Experience in Ultrasonic Flaw Estimation and its Excavation on the Weldments of Nuclear Pressure Vessels (원전 압력용기 용접부 초음파탐상, 결함크기 평가 및 결함 수리 경험)

  • Lee, J.P.;Park, D.Y.;Lim, H.T.;Kim, B.C.;Joo, Y.S.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.11 no.1
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    • pp.52-60
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    • 1991
  • The importance and role of preservice and inservice inspection(PSI/ISI) for nuclear power plant components are intimately related to plant design, safety, reliability and operation etc.. The Korea Atomic Energy Research Institute(KAERI) has been performing PSI/ISI in Korea since the PSI of Kori nuclear power plant, unit 1 had been performed in 1977. KAERI has localized PSI/ISI technology and has done much experience in ultrasonic flaw detection, evaluation and its excavation on the weldments of large pressure vessels. The results of flaw estimation using ultrasonic examination are compared with the actual flaw sizes revealed by field excavation. KAERI's experience regarding PSI/ISI was described and some discussions were added.

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Critical Success Factors for Nuclear Power Plant Construction Projects (원전건설의 성공적인 시공을 위한 핵심성공요인(CSFs) 도출)

  • Shin, Gisung;Bang, Seongdeok;Kim, Kyeongseok;Kim, Hyoungkwan
    • Korean Journal of Construction Engineering and Management
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    • v.18 no.1
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    • pp.48-57
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    • 2017
  • The construction of the first nuclear power plant (Kori #1) in Korea started in 1971, Korea operates 24 nuclear power plants and is constructing 4 in 2015. During about 45 years of construction experience, insufficient studies have been investigated for the identification of critical success factors(CSFs) for nuclear power plant construction. Based on literature reviews and focus group interviews, this study presented a list of CSFs for construction of nuclear power plants. A survey for validating the results of CSFs was conducted with 164 experts. This study indicates that attentions should be placed upon the lowest price-based contract awarding policy, the need for reasonable pricing standard implementation, database development, and deployment for experienced nuclear power plant construction workers, identification and nurturing of competitive subcontractors, and minimization of lag times in construction activities.

Development and Actual Application of Governor Program to Nuclear Steam Turbine (원자력 증기터빈 조속기 프로그램 개발 및 실증 적용)

  • Choi, In-Kyu;Kim, Jong-An;Park, Doo-Yong;Woo, Joo-Hee
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.24 no.4
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    • pp.116-122
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    • 2010
  • This paper describes the up-grade of the turbine governor for steam turbine due to its poor operation from long time use. The analog type governor of the unit 1 in Kori nuclear power plant in Korea was removed and the new digital type turbine governor was developed and installed. The procedure for the actual application, site adaptability test using dynamic simulator and the result of actual operation are described here. And the program for nuclear steam turbine is suggested here.

A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant

  • Kim, Sun Il;Lee, Hak Yun;Song, Jong Soon
    • Nuclear Engineering and Technology
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    • v.50 no.7
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    • pp.1088-1098
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    • 2018
  • Kori unit #1, which is the first commercial nuclear power plant in Korea, was permanently shutdown in June 2017, and it is about to be decommissioned. Currently in Korea, researches on the decommissioning technology are actively conducted, but there are few researches on workers internal exposure to radioactive aerosol that is generated in the process of decommissioning nuclear power plants. As a result, the over-exposure of decommissioning workers is feared, and the optimal working time needs to be revised in consideration of radioactive aerosol. This study investigated the annual exposure limits of various countries, which can be used as an indicator in evaluating workers' internal exposure to radioactive aerosol during pipe cutting in the process of decommissioning nuclear power plants, and the growth and dynamics of aerosol. Also, to evaluate it, the authors compared/analyzed the cases of aerosol generated when activated pipes are cut in the process of nuclear power plants and the codes for evaluating internal exposure. The evaluation codes and analyzed data conform to ALARA, and they are believed to be used as an important indicator in deriving an optimal working time that does not excess the annual exposure limit.