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首页> 外文期刊>Annals of nuclear energy >Sensitivity analysis of in-pile critical heat flux experiments in TREAT for characterization of RIA power-transient effects
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Sensitivity analysis of in-pile critical heat flux experiments in TREAT for characterization of RIA power-transient effects

机译：桩临界热通量实验敏感性分析治疗RIA电力瞬态效应的特征

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A reactivity-initiated accident (RIA) is one type of postulated design basis accident (DBA) that can cause a departure from nucleate boiling (DNB) event in pressurized-water reactors (PWRs). A DNB occurrence and its consequences depend on the thermophysical properties of the fuel components and coolant, characteristics of the transient energy insertion into the fuel rod, and the onset of the critical heat flux (CHF) phenomenon. To leverage the restart of the Transient Reactor Test (TREAT) Facility, an effort is currently underway to better understand the cladding-to-coolant heat transfer mechanisms and the CHF phenomenon under fast-transient irradiation conditions. This paper characterizes the impact of power transients on the thermal-hydraulic behavior of a TREAT Facility reactor heater rodlet CHF experiment to provide the priority of parameters that need to be investigated for an improved CHF model. Sobol sensitivity analysis methods and the Reactor Excursion and Leak Analysis Program (RELAP5-3D) code were used to identify key input parameters on the uncertainty in the prediction of peak outer- and inner-surface temperatures of the heater tube, as well as the time of the DNB event. A series of sensitivity analyses revealed the total energy deposition on the tube and the transient effects of power pulse had large impacts on the maximum temperatures. The CHF multiplier had the largest impact on the time occurrence of CHF. The overall results show the energy deposition rate in the tube is the most influencing factor to the manifestation of CHF and the resulting thermal-hydraulic behaviors of the tube. The multiplier for the CHF, which is interpreted as the predicted CHF value, has the largest Sobol indices for the time of the CHF in all cases, since it directly determines the occurrence of CHF. It is inferred that the uncertainties in the thermal-hydraulic behaviors of fuels increase with respect to the key parameters as the power pulse becomes broader, and an accurate estimation of the energy deposition rate is required to reduce the uncertainty in the evaluation of the integrity of fuel if the CHF is expected to occur near the peak power. The outputs are expected to provide rigorous interpretation of ongoing in-pile CHF experiments in the TREAT Facility reactor regarding thermal-hydraulic behavior of the fuel system aiming for a new transient in-pile CHF model. (C) 2021 Elsevier Ltd. All rights reserved.
机译：反应性引发事故（RIA）是一种假定的设计基准事故（DBA）的，可能会导致从泡核沸腾（DNB）事件压水反应堆（压水堆）出发。甲DNB发生及其后果取决于燃料组件和冷却剂，瞬态能量插入燃料棒，和的临界热通量（CHF）现象的发生的特性的热物理性能。要利用瞬态反应堆试验（TREAT）基金的重启，努力正在进行，以更好地了解包到冷却剂的热传递机制和快速瞬态照射条件下CHF现象。本文表征功率瞬态的一个TREAT设施反应器加热器小棒CHF实验的热工水力行为的影响，以提供需要被研究一种改进的CHF模型参数的优先级。 Sobol灵敏度分析方法和反应器游览和泄漏分析程序（RELAP5-3D）码被用来对峰outer-和加热器管的内表面的温度的预测的不确定性确定关键的输入参数，以及时间的DNB事件。一系列灵敏度分析揭示在管的总能量沉积和功率脉冲的瞬态效应对的最高温度大的影响。乘数对心衰的发生时间的影响最大瑞郎。总体结果表明在管中的能量沉积速率是CHF的表现形式和管子的所得热工水力行为影响最大的因素。为CHF，这被解释为预测值CHF，乘法器具有用于在所有情况下，CHF的时间最大Sobol指数，因为它直接决定CHF的发生。据推断，在燃料的热工水力行为的不确定性增加相对于所述关键参数作为功率脉冲变得更宽，并且能量沉积速率的准确估计，需要以减少的完整性的评价的不确定性如果燃料瑞郎有望接近峰值功率发生。输出预计可提供的关于燃料系统瞄准一个新的瞬态堆内CHF模型的热工水力行为TREAT设施反应堆正在进行中桩CHF实验严谨的解释。 （c）2021 elestvier有限公司保留所有权利。

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