首页> 外文会议>International Conference on Nuclear Engineering: Abstracts >HEAT TRANSFER CHARACTERISTICS ARO ND A SINGLE HEATED ROD IMMERSED IN SODI M POOL WITH GAS JET INJECTION
【24h】

HEAT TRANSFER CHARACTERISTICS ARO ND A SINGLE HEATED ROD IMMERSED IN SODI M POOL WITH GAS JET INJECTION

机译:气体喷射射流浸入Sod M池中的单根加热棒的传热特性

获取原文

摘要

In a steam generator using liquid sodium, water intensely reacts with sodi m when it leaks out from a heat transfer tube. It is important to evaluate the influence of sodium-water reaction to surrounding tubes and the shell. Hence, it has been desired to develop the simulation code for the evaluation of sodium-water reaction. From this viewpoint, the Japan Nuclear Cycle is now developing the SERAPHIM code. We reported a preliminary study to establish an experimental method for a single heated rod immersed in sodium pool with steam jet impingement planned in the near future as well as to obtain a preliminary data to verify the adequacy of SERAPHIM code. We first measured local and mean heat transfer coefficients around a horizontal single heated rod immersed in a water pool and a sodi m pool with a limited vol me in the experimental apparatus. It was confirmed that the mean heat transfer coefficients fairly agreed with the existing data for natural convection in water and sodium. Secondary we measured local and mean heat transfer coefficients aro nd a horizontal single heated rod with Ar gas jet impingement immersed in the limited water pool and in the limited sodium pool. It was clearly observed that the local heat transfer coefficients in the sodi m pool keep almost the same values in every angle regardless of increase in Ar gas jet velocity varied from about 8.7m/s to about 78m/s. On the other hand, it was confirmed in the water pool that local heat transfer coefficients on the forward stagnation side exposed in the Ar gas jet impingement increase with increasing the jet velocity while the local heat transfer coefficients on the opposite surface keep almost same values regardless of increase in the velocity.
机译:在使用液态钠的蒸汽发生器中,当水从传热管泄漏时,水会与钠发生强烈反应。评估钠水反应对周围管子和外壳的影响非常重要。因此,期望开发用于评估钠水反应的模拟代码。从这个角度来看,日本核循环正在开发SERAPHIM代码。我们报告了一项初步研究,以建立将单个加热棒浸入钠池中并在不久的将来计划进行蒸汽喷射撞击的实验方法,并获得初步数据以验证SERAPHIM代码的适用性。我们首先测量了浸没在实验装置中水和碱液池中的水平单根加热棒周围的局部传热系数和平均传热系数。可以确定,平均传热系数与水和钠中自然对流的现有数据完全吻合。其次,我们在水平的单个加热棒周围测量了局部传热系数和平均传热系数,并在受限制的水池和有限的钠池中浸入了Ar气体射流。清楚地观察到,无论Ar气体喷射速度的增加从大约8.7m / s到大约78m / s,在每个角度中,钠池中的局部传热系数都保持几乎相同的值。另一方面,可以确认在水池中,在Ar气体的射流冲击下暴露的正停滞侧的局部传热系数随着射流速度的增加而增加,而相反面的局部传热系数几乎保持相同的值。速度的增加。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号