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海洋条件下螺旋管内流动沸腾数值模拟

Numerical simulation of flow boiling in helically coiled tubes under ocean conditions

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【作者】 叶子翔; 沈昕祎; 程坤; 张旭; 朱晨昕; 唐靖雨; 边浩志;

【Author】 YE Zi-xiang;SHEN Xin-yi;CHENG Kun;ZHANG Xu;ZHU Chen-xin;TANG Jing-yu;BIAN Hao-zhi;College of Nuclear Science and Technology,Harbin Engineering University;Nuclear Power Institute of China;

【机构】 哈尔滨工程大学核科学与技术学院; 中国核动力研究设计院;

【摘要】 在海洋条件下,核动力系统产生的摇摆、起伏等运动会对反应堆热工水力特性产生影响。为研究螺旋管式直流蒸汽发生器在摇摆、起伏及摇摆-起伏复合条件下的沸腾换热特性,本研究基于三维精细化CFD软件,采用VOF多相方法和Rohsenow沸腾模型,在摇摆辐角为30°、周期为7 s的摇摆工况下,起伏加速度为0.5g、周期为4 s的典型起伏工况下开展了单一海洋条件的影响研究,同时耦合分析了摇摆-起伏复合条件下的流动与传热特性。研究表明,海洋条件下设备的时均换热性能增强,螺旋管内对流换热系数瞬态特性出现波动,摇摆条件下最大增幅达12.509%;摇摆-起伏复合条件下,随着起伏加速度的增加,最大增幅可达20.392%。

【Abstract】 Under ocean conditions,the rolling and heaving motion of the nuclear power system will affect the thermal and hydraulic characteristics of the reactor.In order to study the boiling heat transfer characteristics of helical tube direct current steam generator under rolling,heaving and compound conditions,this study is based on three-dimensional refined CFD software,adopts VOF multiphase method and Rohsenow boiling model,the impact of a single ocean condition was studied under typical rolling conditions with a rolling angle of 30°,a period of 7 seconds,typical heaving conditions with a heaving acceleration of 0.5 g,and a period of 4 seconds,and the flow and heat transfer characteristics under the combined rolling and heaving condition are coupled.The results show that the time-uniform heat transfer performance of the equipment is enhanced under ocean conditions,and the convective heat transfer coefficient in the spiral tube fluctuates,and the maximum increase is 12.509% under rolling conditions.Under the rolling and heaving compound condition,with the increase of the heaving acceleration,the variation law of convective heat transfer coefficient deviates from the periodic fluctuation under the pure rolling condition,and the maximum increase can reach 20.392%.

【基金】 国家自然科学基金(12005215)
  • 【会议录名称】 中国核科学技术进展报告(第八卷)中国核学会2023年学术年会论文集 第9册 核安全 核设备 反应堆热工流体力学
  • 【会议名称】中国核学会2023年学术年会
  • 【会议时间】2023-10-17
  • 【会议地点】中国陕西西安
  • 【分类号】TL333
  • 【主办单位】中国核学会
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