• 제목/요약/키워드: Nuclear power program

검색결과 508건 처리시간 0.03초

Comparison between a 13-session and One-time Program on Korean Elementary, Middle and High School Students' Understanding of Nuclear Power

  • Han, Eun Ok;Choi, YoonSeok;Lim, YoungKhi
    • Journal of Radiation Protection and Research
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    • 제42권1호
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    • pp.56-62
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    • 2017
  • Background: To help future generations make accurate value judgments about nuclear power generation and radiation, this study will provide an effective education plan suitable for South Korea by applying and analyzing programs for the understanding of nuclear power within the diversely operated programs in the current Korean education system. Materials and Methods: This study analyzed the difference in educational effects by operating a 13-session regular curriculum for one semester and a one-session short-term curriculum from March to July 2016. Results and Discussion: As a result of operating a 13-session model school and a one-time educational program to analyze behavior changes against the traditional learning model, it was found that all elementary, middle and high school students showed higher acceptability of nuclear power in South Korea. The variation was greater for the model school than the short-term program. Conclusion: To prevent future generations from making biased policy decisions stemming from fear regarding nuclear power, it is necessary to bolster their value judgments in policy decisions by acquiring sufficient information about nuclear power generation and radiation through educational programs.

ESTABLISHMENT OF A MAINTENANCE PROGRAM TO PREVENT LOSS OF OFFSITE POWER IN NUCLEAR POWER PLANTS

  • Lee, Eun-Chan;Na, Jang-Hwan
    • Nuclear Engineering and Technology
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    • 제45권6호
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    • pp.791-794
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    • 2013
  • Since the Fukushima accident in 2011, the importance of the electrical systems in nuclear power plants (NPPs) has been emphasized. The result has been that NPP regulators are enhancing their monitoring of loss of offsite power (LOOP) events. Korea Hydro & Nuclear Power Co. (KHNP) is reviewing the status and issues related to LOOPs, and is attempting to establish specific countermeasures to prevent LOOPs, because they can have severe consequences in the complicated maintenance schedule during an outage. A starting point for preventing LOOPs is the control of the loss of voltage (LOV)-initiating components. In order to reflect this in the risk assessment program, an LOV monitor is being developed for use during plant outages.

PROSPECTIVE ON DEVELOPMENT OF NUCLEAR POWER AND THE ASSOCIATED FUEL CYCLE IN CHINA

  • Gu Zhongmao;Liu Changxin;Fu Manchang
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 Proceedings of The 6th korea-china joint workshop on nuclear waste management
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    • pp.156-164
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    • 2005
  • The challenges China is facing in energy security are briefly discussed. Then, the development of nuclear power in China in the first half of 21 st century is envisioned, and it is expected that Generation-3 PWR nuclear power plants (NPPs) would be the leading units of nuclear power in the coming $30\~40$ years. As part of the nuclear power program, the R&D work on nuclear fuel cycle is generally proposed.

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원전 재료열화 평가프로그램 개발 (Development of Materials Degradation Evaluation Program for Nuclear Power Plants)

  • 신호상;오영진
    • 한국압력기기공학회 논문집
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    • 제7권3호
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    • pp.23-29
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    • 2011
  • The renewed global interest in nuclear power has arisen from the need to reduce greenhouse gas emissions and to provide sufficient electricity for a growing global population before the accident at Fukushima Dai-ichi nuclear power plant in Japan. In spite of the safety issues of nuclear power plants raised by the ongoing Japanese nuclear crisis, many countries with nuclear power plants (NPPs) are still implementing license extensions of 10~20 years, and even consideration is being given to the concept of life-beyond-60, a further period of license extension from 60 to 80 years. To solving the materials aging problem is integral to its success. To evaluate the plant aging phenomena, a lot of background information such as materials and environment of the parts of the reactor and plant systems is needed by the experts. Information on degradation mechanisms is also used. In this paper, a materials degradation evaluation program called OnMDE-SYS (On-line Materials Degradation Evaluation System) is introduced. The developed program provides a variety of information on the materials and stressors as well as operational experience to the experts. It is also anticipated that the experts can perform materials degradation assessment on the web directly by referring to domestic and international information about the degradation of a nuclear power plants through OnMDE-SYS.

Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition

  • Gui, Minyang;Tian, Wenxi;Wu, Di;Chen, Ronghua;Su, G.H.;Qiu, Suizheng
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.446-454
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    • 2021
  • Critical heat flux (CHF) has traditionally been evaluated using look-up tables or empirical correlations for nuclear power plants. However, under complex moving condition, it is necessary to reconsider the CHF characteristics since the conventional CHF prediction methods would no longer be applicable. In this paper, the additional forces caused by motions have been added to the annular film dryout (AFD) mechanistic model to investigate the effect of moving condition on CHF. Moreover, a theoretical model of the natural circulation loop with additional forces is established to reflect the natural circulation characteristics of the loop system. By coupling the system loop with the AFD mechanistic model, a CHF prediction program called NACOM for natural circulation loop under moving condition is developed. The effects of three operating conditions, namely stationary, inclination and rolling, on the CHF of the loop are then analyzed. It can be clearly seen that the moving condition has an adverse effect on the CHF in the natural circulation system. For the calculation parameters in this paper, the CHF can be reduced by 25% compared with the static value, which indicates that it is important to consider the effects of moving condition to retain adequate safety margin in subsequent thermal-hydraulic designs.

원자력발전소 정지형 여자기의 예방정비기준(PMT) 개발 (Development of the Preventive Maintenance Template for Static Exciter in the Nuclear Power Plant)

  • 진수환;박진엽;홍영희
    • 에너지공학
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    • 제20권2호
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    • pp.154-162
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    • 2011
  • 예방정비기준은 기기의 높은 신뢰성을 유지하기 위해 정비방법을 문서화한 것으로 기기별 최적화된 예방정비 항목과 주기를 명시하고 기기의 성능저하 메커니즘을 설명하는 지침서이다. 기존의 기기 또는 설비에 대한 정비전략은 상태감시 정비보다는 일정한 주기가 되면 정비를 수행하는 주기정비가 주된 전략이었다. 본 논문은 원전 정지형 여자기에 대하여 기존의 주기정비 형태가 아닌 상태기반 정비 기법을 강화하고 정비 프로그램을 표준화하여 최적화된 정비전략을 구축하기 위한 예방정비 기준을 개발한 내용으로 기기 신뢰성, 발전소 이용률을 향상시킬 수 있는 기반이 될 것으로 판단된다.