首页> 外文会议>Japan-Korea symposium on nuclear thermal hydraulics and safety >Analysis of Experiments for In-Tube Steam Condensation with Noncondensable Gas at Low Pressure Using the RELAP5/MOD3.2 Code Modified with a Non-Iterative Condensation Model
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Analysis of Experiments for In-Tube Steam Condensation with Noncondensable Gas at Low Pressure Using the RELAP5/MOD3.2 Code Modified with a Non-Iterative Condensation Model

机译:用relap5 / mod3.2代码用非迭代冷凝模型改变低压下脱脂气体管蒸汽冷凝实验

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The standard RELAP5/MOD3.2 code is modified using non-iterative modeling, which is a mechanistic model developed for easy engineering application to simulate steam condensation in the presence of noncondensable gases in a tube. To predict the liquid-side heat transfer coefficients in the modified RELAP5/MOD3.2 code, Nusselt's correlation is used for condensation in a vertical tube and Kim's correlation correlated with the Froude number is used for condensation in a horizontal tube. In the modified code the wall friction in a vertical tube is calculated using the two-phase friction factor correlation proposed by Collier and the interfacial friction factor is calculated using the empirical power-law relationship of Choi. Both the standard and the modified RELAP5/MOD3.2 codes are used to simulate two kinds of vertical in-tube experiments and a horizontally stratified in-tube experiment involving the condensation phenomenon in the presence of noncondensable gas. Two vertical in-tube experiments, PCCS (Passive Containment Cooling System) condensation and reflux condensation experiments, provide data on the steady-state behaviors with typical flow, pressure and air mass fraction conditions likely to be seen in a condensing tube of PCCS and in a U-tube of steam generator in mid-loop operation. The horizontally stratified in-tube experiment represents the direct-contact condensation phenomena in a hot leg of a nuclear reactor. The modeling capabilities of the modified code as well as the standard code for steam condensation in the presence of noncondensable gas are assessed using those three KAIST condensation experiments. The modified code gives better prediction over the data of the three condensation experiments than the standard code. Simulation results of PCCS and reflux condensation experiments show that the local heat transfer coefficients are well predicted with the modified code but they are under-predicted by the default model and over-predicted by the alternative model. The modified code well predicts the experimental void fraction using the two-phase wall friction factor correlation. Simulation results of horizontally stratified condensation experiments show that the modified code predicts the interfacial heat transfer coefficient better than the standard code
机译:使用非迭代建模修改标准RELAP5 / MOD3.2代码,该模型是开发的机械模型,以便于工程应用,以模拟在管中不可调味的气体存在下的蒸汽冷凝。为了预测改进的RELAP5 / MOD3.2码中的液体侧传热系数,NUSERELT的相关性用于垂直管中的凝结,并且与弗劳德数相关的KIM的相关性用于水平管中的冷凝。在修改的代码中,使用煤矿提出的两相摩擦因子相关性来计算垂直管中的壁摩擦,并且使用CHOI的经验幂律关系计算界面摩擦因子。标准和改进的RELAP5 / MOD3.2代码都用于模拟两种垂直的内管实验和涉及在不可调味的气体存在下的冷凝现象的水平分层的内管实验。两个垂直的管道实验,PCCS(被动壳体冷却系统)缩合和回流冷凝实验,提供有关典型流动,压力和空气质量分数条件的数据,可能在PCCS的冷凝管中看到中环操作中的蒸汽发生器U形管。水平分层的管内实验代表核反应堆的热腿中的直接接触冷凝现象。使用这三个Kaist缩合实验评估修改代码的建模能力以及在不可缩压的气体存在下存在蒸汽冷凝的标准码。修改的代码对三个冷凝实验的数据提供比标准代码更好地预测。 PCCS和回流冷凝实验的仿真结果表明,用修改的代码良好地预测了局部传热系数,但是通过默认模型和通过替代模型过度预测的预测它们。修改的代码良好地使用两相壁摩擦因子相关性预测实验空隙率。水平分层凝结实验的仿真结果表明,修改的代码预测了比标准代码更好的界面传热系数

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