CMC碳化硅和锆合金包层的多物理场分析

M. Altahhan, Noah McFerran, J. Morrell, M. Avramova
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摘要

核燃料包壳是核反应堆的重要组成部分,选择合适的材料对反应堆的设计至关重要。本文研究了以陶瓷基复合材料(CMC)碳化硅(SiC)为包层材料的17 × 17西屋公司压水堆(PWR)组件的中子性能和燃料性能。材料分析与西屋公司17x17压水堆组件中使用的传统锆合金-4包层进行了比较。分析中使用的代码是密歇根基于并行特性的传输(MPACT)代码加上CTF,北卡罗莱纳州立大学版本的冷却剂在棒阵列两种流体中沸腾(COBRA-TF)代码,以及燃料性能代码BISON以及不确定性分析代码DAKOTA。此外,对燃料球团的环形几何形状进行了建模,以评估其与普通CMC SiC或传统锆合金-4包壳相比的优点。结果发现,在中子方面,CMC SiC具有较低的U-235富集度,从而达到与Zircalloy-4包层相同的燃耗和有效中子增殖因子。从经济成本分析和反应堆运行的角度来看,这些结果都是一个优势。此外,研究还发现,使用CMC SiC材料可以达到西屋PWR组件的各种安全运行标准,如充气压力、燃料包壳接触压力、燃料峰值温度和裂变气体释放标准,其中一些标准的设计余量比使用锆合金-4包壳材料的设计余量更大。此外,一项临界热通量(CHF)研究表明,CMC SiC具有比普通锆合金-4包层更大的热裕度,由于燃料销可以在更大的功率下运行,从而产生更有利可图的燃料循环。对CHFR进行不确定度量化,以评估影响CHFR计算值的最大重要程度。
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Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding
Nuclear fuel cladding is an integral part of nuclear reactors and choosing the proper material is imperative to the design of a reactor. In this paper, the neutronic properties and the fuel performance of a 17 × 17 Westinghouse Pressurized Water Reactor (PWR) assembly using ceramic matrix composites (CMC) Silicone Carbide (SiC) as a cladding material is investigated. The material analysis is compared against traditional Zircaloy-4 cladding used in a 17 × 17 Westinghouse PWR assembly. The codes used in the analysis are the Michigan Parallel Characteristics based Transport (MPACT) code coupled with CTF, the North Carolina State University version of the Coolant Boiling in Rod Arrays Two Fluids (COBRA-TF) code, and the fuel performance code BISON as well as the uncertainty analysis code DAKOTA. Additionally, annular geometry for the fuel pellet is modeled to assess its merit compared to ordinary CMC SiC or traditional Zircaloy-4 claddings. It is found that on the neutronics side, the CMC SiC shows lower achievable U-235 enrichments required to reach the same burnup and effective neutron multiplication factor as Zircalloy-4 claddings. These results are an advantage that can be seen in the economic cost analysis done and additionally from the reactor operation point of view. Also, it is found that the different criteria of safe operation of Westinghouse PWR assemblies like the plenum pressure, the fuel-cladding contact pressure, the peak fuel temperature, and the fission gas release criteria are all achieved with CMC SiC with some criteria having larger design margins than of the Zircaloy-4 cladding. Furthermore, a critical heat flux (CHF) study shows that CMC SiC has even larger thermal margins than the ordinary Zircaloy-4 cladding, resulting in a more profitable fuel cycle due to the greater amount of power that the fuel pins can be operated at. An uncertainty quantification for the CHF Ratio (CHFR) is also done to assess the largest magnitudes of importance that affect the CHFR calculated.
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