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Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

机译:使用Thales子信道代码在低流量条件下反应堆核心分析

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During the operation of PWR (Pressurized Water Reactor) nuclear power plant, the minimum DNBR (Departure from Nucleate Boiling Ratio) should be maintained within the Tech. Spec. LCO (Limiting Conditions for Operation) to satisfy the acceptance criteria during AOO (Anticipated Operational Occurrence) and event condition. For the DNBR analysis, the calculation of the flow and energy fields is required. Some events may experience the low flow condition if the LOOP (Loss of Offsite Power) is occurred. The reactor core analysis at low flow condition is classified into two ways. One is for the power generation of the reactor core and the other is for DNBR calculation of hot node. Generally, the flow analysis for core power generation is more difficult. The representative event which experienced the low flow condition is SLB (Steam Line Break) event. During the SLB event with LOOP, the reactor core is tripped and all RCPs (Reactor Coolant Pump) are stopped. As a result, the flow rate and pressure in reactor core decrease and the peaking factor is relatively high compared to a nominal operating condition. For the prediction of state in the PWR reactor core, the reactor core analysis at low flow condition is performed using the subchannel code THALES (Thermal Hydraulic AnaLyzer for Enhanced Simulation of core) developed by KEPCO Nuclear Fuel. Since the subchannel analysis code was developed to solve the reactor core flow field at the high axial flow rate and pressure condition, the convergence at the low flow condition such as SLB is very difficult. Therefore, most of subchannel analysis codes fail to obtain the converged flow field at very low flow and high power, which has resulted to insufficient research of 3 dimensional analysis of SLB event. This paper will show why we have a trouble to obtain the converged result for the reactor core analysis at low flow condition. And we show the high distortion characteristics of the flow and energy fields at the low flow condition by using subchannel analysis code. Through the core flow analysis at low flow condition, it is verified that subchannel code THALES can predict reasonable results despite of the extreme condition and that the distortion of the flow and energy field is huge.
机译:在PWR(加压水反应堆)核电站的运行过程中,应在技术内保持最低DNBR(核心沸腾率的偏离)。规格。 LCO(限制运行条件)以满足AOO(预期运营发生)和事件条件期间的验收标准。对于DNBR分析,需要计算流和能量场。如果发生循环(异地电源的丢失),某些事件可能会遇到低流量状态。低流量条件下的反应器核心分析被分为两种方式。一个是用于反应器核的发电,另一个是用于热节点的DNBR计算。通常,核心发电的流量分析更加困难。经历了低流量条件的代表性事件是SLB(Steam Dium Break)事件。在带环的SLB事件期间,钳子钳位,所有RCP(反应器冷却剂泵)都停止。结果,与标称操作条件相比,反应堆核心减小的流速和压力相对较高。为了预测PWR反应器核心,使用Kepco核燃料开发的子信道码Thales(热液压分析仪的热液压分析仪进行低流量条件下的反应器核心分析。由于开发了子信道分析代码以在高轴流速率和压力条件下解决反应器芯流场,因此诸如SLB的低流量条件下的收敛非常困难。因此,大多数子信道分析代码不能在非常低的流量和高功率下获得会聚流场,这导致SLB事件的3维分析的研究不足。本文将展示为什么我们在低流量条件下获得反应堆核心分析的融合结果。并且我们通过使用子信道分析代码来显示低流量条件下流动和能量场的高失真特性。通过低流量条件下的核心流量分析,验证了虽然虽然存在极端条件,但是,尽管存在极端条件,并且流动和能量场的变形是巨大的,所以子信道代码码可以预测合理的结果。

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