首页> 外文会议>Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety Oct 15-18, 2000 Denki Bldg., Chuo-ku, Fukuoka, Japan >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:使用非迭代冷凝模型修改的RELAP5 / MOD3.2代码对低压不凝性气体进行管内蒸汽冷凝的实验分析

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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:标准RELAP5 / MOD3.2代码使用非迭代建模进行了修改,该模型是一种机械模型,为易于工程应用而开发,可在管道中存在不可冷凝气体的情况下模拟蒸汽冷凝。为了在修改后的RELAP5 / MOD3.2代码中预测液体侧的传热系数,将Nusselt相关用于竖管中的冷凝,将Kim与Froude数相关的相关用于水平管中的冷凝。在修改后的代码中,垂直管中的壁摩擦力是使用科利尔(Collier)提出的两相摩擦系数相关性来计算的,而界面摩擦因数是根据Choi的经验幂律关系来计算的。标准代码和修改后的RELAP5 / MOD3.2代码均用于模拟两种垂直管内实验和水平分层管内实验,其中涉及在不可凝气体存在下的冷凝现象。两个垂直的管内实验,即PCCS(被动安全壳冷却系统)冷凝和回流冷凝实验,提供了在PCCS冷凝管和冷凝器中可能会看到的典型流量,压力和空气质量分数条件下的稳态行为数据。蒸汽发生器的U型管处于中环运行状态。水平分层的管内实验代表了核反应堆热段中的直接接触冷凝现象。使用这三个KAIST冷凝实验评估了修改代码的建模能力以及在不凝性气体存在下蒸汽冷凝的标准代码。与标准代码相比,修改后的代码可更好地预测三个冷凝实验的数据。 PCCS和回流冷凝实验的仿真结果表明,使用改进的代码可以很好地预测局部传热系数,但是默认模型对它们的预测不足,而替代模型则对它们的预测过高。修改后的代码使用两相壁摩擦系数相关性很好地预测了实验空隙率。水平分层凝结实验的仿真结果表明,改进的代码比标准代码预测界面传热系数更好

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