• Title/Summary/Keyword: ocean nuclear power plant

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A new design concept for ocean nuclear power plants using tension leg platform

  • Lee, Chaemin;Kim, Jaemin;Cho, Seongpil
    • Structural Engineering and Mechanics
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    • v.76 no.3
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    • pp.367-378
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    • 2020
  • This paper presents a new design concept for ocean nuclear power plants (ONPPs) using a tension leg platform (TLP). The system-integrated modular advanced reactor, which is one of the successful small modular reactors, is mounted for demonstration. The authors define the design requirements and parameters, modularize and rearrange the nuclear and other facilities, and propose a new total general arrangement. The most fundamental level of design results for the platform and tendon system are provided, and the construction procedure and safety features are discussed. The integrated passive safety system developed for the gravity based structure-type ONPP is also available in the TLP-type ONPP with minor modifications. The safety system fully utilizes the benefits of the ocean environment, and enhances the safety features of the proposed concept. For the verification of the design concept, hydrodynamic analyses are performed using the commercial software ANSYS AQWA with the Pierson-Moskowitz and JONSWAP wave spectra that represent various ocean environments and the results are discussed.

Study on Optimization of Dissimilar Friction Welding of Nuclear Power Plant Materials and Its Real Time AE Evaluation (원자력 발전소용 이종재 마찰용접의 최적화와 AE에 의한 실시간 평가에 관한 연구)

  • 권상우;오세규;유인종;황성필;공유식
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2000.10a
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    • pp.42-46
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    • 2000
  • In this paper, joints of Cu-1Cr-0.1Zr alloy to STS316L were performed by friction welding method. Cu-1Cr-0.1Zr alloy is attractive candidate as nuclear power plant material and exibit the best combination of high sts good electrical and thermal conductivity of any copper alloy examined. The stainless steel is a structural material who alloy acts as a heat sink material for the surface heat flux in the first wall. So, in this paper, not only the develop optimizing of friction welding with more reliability and more applicabililty but also the development of in-process rear quility(such as strength and toughness) evaluation technique by acoustic emission for friction welding of such nuclear component of Cu-1Cr-0.1Zr alloy to STS316L steel were performed.

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OTEC System using the Condenser Effluent from Nuclear Power Plant a feasibility study (원자력 발전소의 온배수를 이용한 해양온도차 발전의 타당성 검토)

  • Shin, Sangwoong;Chun, Wongee
    • 한국신재생에너지학회:학술대회논문집
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    • 2010.06a
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    • pp.238.2-238.2
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    • 2010
  • Recently, environmental pollution and energy depletion problems have been issued over the world. For this reason, many renewable systems have been developing. Of these, the Ocean Thermal Energy Conservation(OTEC) is drawing attention as the upcoming alternative energy source. In this paper, the efficiency of each of OTEC which harness the effluent from nuclear power plant was analyzed by using computer calculation. The result, shows that Ul-jin Nuclear Power Plant is the best place geographically and the regenerative cycle is most outstanding performance cycle for OTEC. The difference of temperature between surface water and deep water temperature should be greater than $20^{\circ}C$ in order to increase the efficiency.

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Radioactivity data analysis of 137Cs in marine sediments near severely damaged Chernobyl and Fukushima nuclear power plants

  • Song, Ji Hyoun;Kim, TaeJun;Yeon, Jei-Won
    • Nuclear Engineering and Technology
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    • v.52 no.2
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    • pp.366-372
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    • 2020
  • Using several accessible published data sets, we analyzed the temporal change of 137Cs radioactivity (per unit mass of sample) in marine sediments and investigated the effect of the water content of sediment on the 137Cs radioactivity, to understand the behavior of 137Cs present in marine environments. The 137Cs radioactivity in sediments decreased more slowly in the Baltic Sea (near the Chernobyl nuclear power plant) than in the ocean near the Fukushima Daiichi nuclear power plant (FDNPP). The 137Cs radioactivity in the sediment near the FDNPP tended to increase as the water content increased, and the water content decreased at certain sampling sites near the FDNPP for several years. Additionally, the decrease in the water content contributed to 51.2% of the average 137Cs radioactivity decrease rate for the same period. Thus, it may be necessary to monitor both the 137Cs radioactivity and the water content for marine sediments to track the 137Cs that was discharged from the sites of Chernobyl and Fukushima nuclear power plants where severe accidents occurred.

A Buoyant Combined Solar-Wave Power Generation and Its Application for Emergency Power Supply of Nuclear Power Plant (부유식 태양광-파력 복합발전 개념 및 원자력발전소 비상전원을 위한 응용)

  • Cha, Kyung-Ho;Kim, Jung-Taek
    • New & Renewable Energy
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    • v.7 no.4
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    • pp.37-41
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    • 2011
  • This paper presents a Combined solar-wave Power Generation (CPG) concept that the CPG unit is maintained as buoyant at the level of sea water and it is also supported by a submerged tunnel, with the aim of supplying emergency electric power during the station blackout events of nuclear power plants. The CPG concept has been motivated from the 2011 Fukushima-Daiichi Accidents due to the loss of both offsite AC power and emergency diesel power caused by natural hazards such as earthquake and tsunami. The CPG is conceptualized by applying different types and different sites for emergency power generation, in order to reduce common cause failures of emergency power suppliers due to natural hazards. Thus, the CPG can provide a new mean for supplying emergency electric power during station blackout events of nuclear power plants. For this application, the CPG requirements are described with a typical configuration at the ocean side of a submerged tunnel.

A Standard Guide to Physical Oceanographic Survey of the Effect of Thermal Discharge from a Nuclear Power Plant (원자력발전소 온배수 영향 해양물리분야 조사의 표준지침)

  • Lee, Jae-Hak;Ro, Young-Jae;Cho, Yang-Ki
    • The Sea:JOURNAL OF THE KOREAN SOCIETY OF OCEANOGRAPHY
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    • v.12 no.1
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    • pp.43-49
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    • 2007
  • The methods of physical oceanographic surveys to examine the effect of thermal discharge from nuclear power plants in Korea have been reviewed and a standard guide to the survey is proposed. It is desirable that in situ observation and numerical thermal diffusion modeling are conducted simultaneously to describe the variation in temperature distribution affected by thermal discharge from a power plant because any observation or numerical modeling alone has limits to do so quantitatively. It is suggested that the field observation must be based on the concept of heat budget modeling considering all artificial and natural heat sources/sinks around the power plant. Any results from numerical modeling must reach to a certain statistical significance level to use for a standard temperature distribution. In addition, the development of standard numerical codes is proposed to improve the problems shown in the past numerical circulation and diffusion modelling.

Cycle Simulation on OTEC System using the Condenser Effluent from Nuclear Power Plant (원자력발전소 온배수를 이용한 해양 온도차발전 사이클 해석)

  • Kim, Nam-Jin;Jeon, Young-Han;Kim, Chong-Bo
    • Journal of the Korean Solar Energy Society
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    • v.27 no.3
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    • pp.37-44
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    • 2007
  • For the past few years, the concern for clean energy has been greatly increased. Ocean Thermal Energy Conversion(OTEC) power plants are studied as a viable option for the supply of clean energy. In this paper, the thermodynamic performance of OTEC cycle was examined. Computer simulation programs were developed under the same condition and various working fluids for closed Rankine cycle, regeneration cycle, Kalina cycle, open cycle and hybrid cycle. The results show that the regeneration cycle using R125 showed a 0.17 to 1.56% increase in energy efficiency, and simple Rankine cycle can generate electricity when the difference in warm and cold sea water inlet temperatures are greater than $15^{\circ}C$. Also, the cycle efficiency of OTEC power plant using the condenser effluent from nuclear power plant instead of the surface water increased about 2%.

Study on Optimization of Dissimilar friction Welding of Nuclear Power Plant Materials (Cu Alloy/STS316L) and Its Real Time AE Evaluation (원자력 발전소용 이종재(Cu 합금/STS316L) 마찰용접의 최적화와 AE에 의한 실시간 평가에 관한 연구)

  • 유인종;권상우;황성필;공유식;오세규
    • Journal of Ocean Engineering and Technology
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    • v.15 no.2
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    • pp.88-93
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    • 2001
  • In this paper, joints of Cu-1Cr-0.1Zr alloy to STS316L were performed by friction welding method. Particularly, Cu-1Cr-0.1Zr alloy is attractive candidate as nuclear power plant material and exibit the best combination of high strength and good electrical and thermal conductivity of any copper alloy examined. The stainless steel is a structural material while copper alloy acts as a heat sink material for the surface heat flux in the first wall. So, in this paper, not only the development of optimizing of friction welding with more reliability and more applicability but also the development of in-process real-time weld quality (such as strength and toughness) evaluation technique by acoustic emission for friction welding of such nuclear reactor component of Cu-1Cr-0.1Zr alloy to STS316L steel sere performed.

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