首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments
【24h】

Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments

机译:燃料束CHF的热损失模拟和不确定性分析及其他大规模热工实验

获取原文

摘要

Heat transfer experiments play a key role in exploring the underlining mechanisms of nuclear reactor thermal hydraulic phenomena. Large scale heat transfer tests, especially for rod bundle critical heat flux (CHF) experiments, generally utilize high power to achieve necessary operation conditions including wide ranges of temperature, flow, pressure, etc.. Temperature differences between test boundary, the boarding equipment, secondary flow housing, and the surrounding environment can be significant. Besides, heavy mass components, such as flanges, housing, and adaptor, can also serve as large heat sinks or heat sources leading to potentially large heat loss/gain and measurement uncertainty. Due to the complication of the installation and coupling of thermal-hydraulic conditions between inner and outer flow paths, direct measurement of heat loss/heat gain often becomes very difficult or nearly impossible. Furthermore, if there is a secondary layer of isolation fluid with potential natural circulation under various transient and steady operations, the total heat loss could have rather complicated dependency on operating conditions. When the total heating power is measured, reliable heat loss estimation is essential for accurate experimental measurements. As for a large scale test facility, different scales, experimental configurations, and operating conditions might lead to different heat loss. This paper presents a case example of heat loss/gain for a high pressure fuel assembly CHF test facility. In this CHF test loop, the test section consists of an inner flow path with an outer surrounding chamber filled with stagnant coolant that might present a significant source of heat loss/heat gain resulting from natural circulation in the surrounding chamber. System code RELAP 5 is used to simulate the test section and the surrounding systems under typical CHF test conditions. The simulated results are further compared to experimental data to verify the model's feasibility.
机译:传热实验在探索核反应堆热水现象的机理中起着关键作用。大规模传热测试,特别是对于棒束临界热通量(CHF)实验而言,通常会利用大功率来实现必要的操作条件,包括宽范围的温度,流量,压力等。测试边界,登机设备,二次流罩,以及周围环境可能很重要。此外,重质量的组件(例如法兰,外壳和适配器)也可以用作大型散热器或热源,从而导致潜在的较大的热量损失/增益和测量不确定性。由于内部和外部流动路径之间的热工条件的安装和耦合的复杂性,直接测量热损失/热增益通常变得非常困难或几乎不可能。此外,如果隔离流体的第二层在各种瞬态和稳定操作下具有潜在的自然循环,则总的热损失可能对操作条件有相当复杂的依赖性。当测量总加热功率时,可靠的热损失估算对于准确的实验测量至关重要。对于大型测试设备,不同的规模,实验配置和操作条件可能会导致不同的热损失。本文介绍了一个高压燃料组件CHF测试设备的热量损失/增益的案例。在此CHF测试回路中,测试部分由内部流动路径组成,外部腔室中充满了停滞的冷却剂,冷却剂可能会由于周围腔室中的自然循环而产生大量的热量损失/热量增加。系统代码RELAP 5用于在典型的CHF测试条件下模拟测试区域和周围的系统。将模拟结果与实验数据进行进一步比较,以验证该模型的可行性。

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