• Title/Summary/Keyword: nuclear power engineering

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A Study on Regenerative OTEC System using the Condenser Effluent of Uljin Nuclear Power Plant (울진 원자력발전소 온배수를 이용한 재생식 해양온도차발전에 대한 연구)

  • Kang, Yun-Young;Park, Sung-Seek;Park, Yun-Beom;Kim, Nam-Jin
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.24 no.7
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    • pp.591-597
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    • 2012
  • 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 study, we examined the thermodynamic performance of the OTEC power system for the production of electric power. Computer simulation programs were developed under the same condition and various working fluids for closed Rankine cycle, regenerative cycle, Kalina cycle, open cycle, and hybrid cycle. The results show that the regenerative cycle showed the best system efficiency. And then we examined the thermodynamic performance of regenerative cycle OTEC power system using the condenser effluent from Uljin nuclear power plant instead of the surface water. The highest system efficiency of the condition was 4.55% and the highest net power was 181 MW.

Study on cognitive load of OM interface and eye movement experiment for nuclear power system

  • Zhang, Jingling;Su, Daizhong;Zhuang, Yan;QIU, Furong
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.78-86
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    • 2020
  • The operation and monitoring (OM) interface is the digital medium between nuclear power system and operators. The cognitive load of OM interface has an important effect on the operation errors made by operator during OM task between operator and computer. The cognitive load model of OM interface is constructed for analysing the composition and influencing factors of OM interface cognitive load. And to study the coping strategies and methods for cognitive load of nuclear power system. An experiment method based on eye movement is proposed to measure the cognitive load of OM interface. Experiment case is carried out with 20 subjects and typical OM interface of a nuclear power system simulator. The OM interface is optimized based on the experiment results. And the results comparison between the original OM interface and the optimized OM interface shows that the cognitive load model and proposed method is valuable contributions in reducing the cognitive load and improving the interaction efficiency of OM tasks.

RCGVS Design Improvement and Depressurization Capability Tests for Ulchin Nuclear Power Plant Units 3 and 4

  • Sung, Kang-Sik;Seong, Ho-Je;Jeong, Won-Sang;Seo, Jong-Tae;Lee, Sang-Keun;Keun hyo Lim;Park, Kwon-Sik;Oh, Chul-Sung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.417-422
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    • 1998
  • he Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3&4(UCN 3&4) has been improved from the Yonggwang Nuclear Power Plant Units 3&4(YGN 3&4) based on the evaluation results for depressurization capability tests performed at YGN 3&4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown Phenomena in order to optimize the orifice size of UCN 3&4 RCGVS. Baesd on these analyses results, the RCGVS orifice size for UCN 3&4 has been reduced to 9/32 inch from the l1/32 inch for YGN 3&4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3&4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation.

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