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首页> 外文期刊>International Journal of Nuclear Energy Science and Technology >Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5
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Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5

机译:使用RELAP5研究用于高级核反应堆的卧式冷凝器中的蒸汽与不可冷凝气体的冷凝

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摘要

Horizontal heat exchangers are used in advanced light water nuclear reactors in their passive cooling systems, such as Residual Heat Removal System (RHRS) and Passive Containment Cooling System (PCCS). Horizontal condensation studies of steam with non-condensable gases mixtures in these heat exchangers are very important. This work presents a comparison between simulation results and experimental data in steady state conditions for some inlet pressure, steam and non-condensable gases (air) inlet mass fractions. The test section was modelled and the simulations were performed with the RELAP5 code. Experimental tests were carried out for 200-400 kPa inlet pressure and 5%, 10%, 15% and 20% of inlet air mass fractions. Comparisons between experimental data and simulation results are presented for 200 kPa and 400 kPa pressure conditions and showed good agreement. New correlations for heat transfer coefficients in these steam-air conditions must be theoretically and experimentally studied and implemented in the RELAP5 code. 【Keywords】steam condensation; non-condensable gases; RHRS; residual heat removal systems; PCCS; passive containment cooling systems; horizontal mcondenser tube; heat exchangers; advanced reactors; ESBWR; RELAP5; nuclear reactors; nuclear power; nuclear energy; simulations.
机译:卧式热交换器在其被动冷却系统(例如,余热排除系统(RHRS)和被动安全壳冷却系统(PCCS))的先进轻水核反应堆中使用。在这些热交换器中,蒸汽与不可冷凝气体混合物的水平冷凝研究非常重要。这项工作对稳态条件下某些进气压力,蒸汽和不可冷凝气体(空气)进气质量分数的仿真结果与实验数据进行了比较。对测试部分进行建模,并使用RELAP5代码进行仿真。针对200-400 kPa的进气压力和5%,10%,15%和20%的进气质量分数进行了实验测试。给出了在200 kPa和400 kPa压力条件下的实验数据和模拟结果之间的比较,并显示出良好的一致性。必须在理论上和实验上研究并在RELAP5代码中实现这些蒸汽空气条件下传热系数的新相关性。 【关键词】蒸汽凝结;不凝性气体; RHRS;余热排除系统; PCCS;被动安全壳冷却系统;水平冷凝器管;热交换器;先进反应堆; ESBWR; RELAP5;核反应堆;核电;核能;模拟。

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    L.A. Macedo; W.M. Torres;

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    Nuclear Engineering Center-CEN,Nuclear and Energy Research Institute,IPEN-CNEN/SP,Av. Prof. Lineu Prestes,2242-Cidade Universitaria,CEP 05508-000 Sao Paulo-SP, Brazil;

    Nuclear Engineering Center-CEN,Nuclear and Energy Research Institute,IPEN-CNEN/SP,Av. Prof. Lineu Prestes,2242-Cidade Universitaria,CEP 05508-000 Sao Paulo-SP, Brazil;

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