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摇摆条件下非能动余热排出系统运行特性的试验与理论研究 被引量:1

Experimental and Theoretical Research on Operational Characteristics of Passive Residual Heat Removal System Under Rolling Motion
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摘要 在摇摆台架上对摇摆条件下的非能动余热排出系统运行特性进行了试验研究。在RELAP5/MOD3.2程序的基础上,采用漂移流模型替代两流体模型,通过修正混合物动量方程、冷凝传热模型,对程序进行改进,利用改进的RELAP5程序,对摇摆条件下的非能动余热排出系统进行了数值模拟,计算结果与试验结果相吻合,误差在10%以内。改进的冷凝换热关系式可较好地用于含有液滴夹带的冷凝换热计算。在摇摆试验中,凝水温度与蒸汽压力波动很小。 The operational characteristics of passive residual heat removal system on the rolling roof were investigated experimentally.On the basis of RELAP5/MOD3.2 code,the two-fluid model was substituted with drift flux model.This code was improved by modifying the mixture momentum equation and condensation heat transfer model.The passive residual heat removal system under rolling motion was simulated by the advanced code,and it was consistent with experiment results.The discrepancy between calculation and experiment results was less than 10%.The advanced condensation heat transfer model can also be used to calculate the condensation heat transfer coefficient with droplet carryover precisely.In the experiments,the fluctuation of condensate temperature and steam pressure was very limited.
出处 《原子能科学技术》 CSCD 北大核心 2010年第5期548-552,共5页 Atomic Energy Science and Technology
关键词 摇摆 非能动余热排出系统 数值模拟 rolling passive residual heat removal system numerical simulation
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  • 1庞凤阁,高璞珍,王兆祥,刘殊一,丁洪河.海洋条件对自然循环影响的理论研究[J].核动力工程,1995,16(4):330-335. 被引量:35
  • 2苏光辉,张金玲,郭玉君秋穗正,喻真烷,贾斗南.海洋条件对船用核动力堆余热排出系统特性的影响[J].原子能科学技术,1996,30(6):487-491. 被引量:19
  • 3谭思超,庞凤阁,高璞珍.摇摆对自然循环传热特性影响的实验研究[J].核动力工程,2006,27(5):33-36. 被引量:36
  • 4曹夏昕,阎昌琪,孙中宁.气-液两相泡状流在摇摆状态下的摩擦压降计算[J].核动力工程,2007,28(1):72-77. 被引量:6
  • 5ISHIDA T, YORITSUNE T. Effects of ship motions on natural circulation of deep sea research reactor DRX[J]. Nuclear Engineering and Design, 2002, 215: 51-67.
  • 6KIMJ H, KIM T W, LEE S M. Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions [J]. Nuclear Engineering and Design, 2001, 207: 21-31.
  • 7HIROYUKI M, SAWADA K, MICHIYUKI K. Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core[J]. Nuclear Engineering and Design, 2002, 215: 69-85.
  • 8Thermohydraulic relationships for advanced water cooled reactors, IAEA-TECDOC-1203 [R]. Vienna: IAEA, 2001.
  • 9于雷.船用核动力装置自然循环运行特性研究[D].武汉:海军工程大学,2008.
  • 10MURATA H, SAWADA K I, MICHIYUKI K S. Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core[J]. NuclEngDes, 2002, 215:69-85.

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