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首页> 外文期刊>Nuclear Technology >Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis
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Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

机译：氟化物盐冷却的高温测试反应堆热工液压执照和不确定性传播分析

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An important fluoride-salt-cooled high-temperature reactor (FHR) development step is to design, build, and operate a test reactor. The uncertainties of the coolant thermophysical properties range between 2% and 20%. This study determines the effects of these high uncertainties by incorporating uncertainty propagation in a thermal-hydraulic safety analysis for test reactor licensing. A hot channel thermal-hydraulic model, Monte Carlo statistical sampling uncertainty propagation, and a limiting safety systems settings (LSSS) approach are combined to ensure sufficient margin to fuel and material thermal limits during steady-state operation while incorporating margin for high-uncertainty inputs. The method calculates LSSS parameters to define safe operation.The methodology is applied to two test reactors currently considered, i.e., China's first Solid Fueled Thorium Molten Salt Reactor (TMSR-SF1) pebble bed design and Massachusetts Institute of Technology's Transportable FHR prismatic core design; two candidate coolants, i.e., flibe (LiF-BeF2) and nafzirf (NaF-ZrF4); and forced flow and natural circulation conditions to compare operating regions and LSSS power (maximum power not exceeding any thermal limits). The calculated operating region accounts for uncertainty (2 sigma) with an LSSS power for forced flows of 25.37 +/- 0.72, 22.56 +/- 1.15, 21.28 +/- 1.48, and 11.32 +/- 1.35 MW for pebble flibe, pebble nafzirf, prismatic flibe, and prismatic nafzirf, respectively. The pebble bed has superior heat transfer with an operating region reduced similar to 10% less when switching coolants and similar to 50% smaller uncertainty than the prismatic. The maximum fuel temperature constrains the pebble bed while the maximum coolant temperature constrains the prismatic due to different dominant heat transfer modes. Sensitivity analysis revealed that (1) thermal conductivity and thus conductive heat transfer dominate in the prismatic design while convection is superior in the pebble bed and (2) the impact of thermophysical property uncertainties is ranked and should be considered for experimental measurements in the following order: thermal conductivity, heat capacity, density, and last, viscosity. Broadly, the methodology incorporates uncertainty propagation that can be used to evaluate parametric uncertainties to satisfy guidelines for nonpower reactor licensing applications, and its application shows that the pebble bed is more attractive for thermal-hydraulic safety. Although the method is developed and evaluated for coolant property uncertainties, it is readily applicable for other parameters of interest.
机译：氟盐冷却高温反应堆（FHR）的重要开发步骤是设计，建造和运行测试反应堆。冷却剂热物理性质的不确定性在2％到20％之间。这项研究通过将不确定性传播纳入用于测试反应堆许可的热工安全性分析中，确定了这些高度不确定性的影响。结合了热通道热工水力模型，蒙特卡洛统计采样不确定性传播和极限安全系统设置（LSSS）方法，以确保在稳态运行期间燃料和材料热极限具有足够的裕量，同时结合了高不确定性输入的裕量。该方法计算LSSS参数以定义安全运行，该方法适用于目前正在考虑的两个测试反应堆，即中国首个固体燃料Thor熔融盐反应堆（TMSR-SF1）卵石床设计和麻省理工学院可运输FHR棱柱形芯设计;两种候选冷却剂，即氟橡胶（LiF-BeF2）和nafzirf（NaF-ZrF4）;以及强制流动和自然循环条件，以比较工作区域和LSSS功率（最大功率不超过任何热极限）。对于卵石flibe，卵石nafzirf，计算出的工作区域使用LSSS功率说明了不确定性（2 sigma），其中强制流为25.37 +/- 0.72、22.56 +/- 1.15、21.28 +/- 1.48和11.32 +/- 1.35 MW ，棱柱形flibe和棱柱形nafzirf。卵石床具有出色的传热性能，与更换棱柱形床相比，更换冷却剂时，工作区域减少了约10％，不确定性减小了约50％。由于不同的主要传热模式，最高燃料温度限制了卵石床，而最高冷却液温度限制了棱柱形。敏感性分析表明，（1）棱柱形设计中的热导率和传导热传递占主导地位，而卵石床中的对流性更高；（2）对热物理性质不确定性的影响进行了排名，应按以下顺序考虑进行实验测量：导热率，热容量，密度以及粘度。广义上讲，该方法结合了不确定性传播，可用于评估参数不确定性，以满足非动力反应堆许可应用指南的要求，其应用表明，卵石床对于热工水力安全性更具吸引力。尽管针对冷却液性能不确定性开发并评估了该方法，但该方法很容易应用于其他感兴趣的参数。

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