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State of knowledge and challenges of U-Si compounds for use in light water reactor accident tolerant fuel designs

机译:用于轻水反应堆事故容忍燃料设计的U-Si化合物的知识和挑战

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Research in uranium silicide binary allows has been renewed in recent years for use in light water reactor accident tolerant fuel concepts due to the high thermal conductivity and hypothesized oxidation tolerance of these compounds The enhanced thermal conductivity would decrease the radial fuel temperature profile, thus decreasing the thermal stresses observed in the system However, research on binary U-Si compounds has historically focused on high fissile density compounds U3S1 and U_3Si_2 in support of the RERTR campaign The properties and microstructures in these studies had a large degree of variability, which required a complete reassessment if these fuels were to be considered for further irradiation testing Experiments at LANL have emphasized fabrication of nearly stoichiometric, low oxygen impurity content specimens of U3S1, U_3Si_2, US_1, and U_3Si_5 for thermophysical properties and oxidation testing to aid modeling and simulation communities with accurate data to predict how these novel fuels will behave in-pile However, many unknowns still remain in the system. Only a handful of the U-Si compounds have had any irradiation testing, which have shown some degree of amorphization and irregular pore shapes making the swelling behavior difficult to predict Fission product silicides have also had limited characterization in the literature with regards to thermodynamics and physical properties Likewise, the impact of phase transformations and phase stability near USi_(2-x) as a function of temperature has largely been overlooked in the literature. This paper will look at the to-date properties of U-Si compounds as a function of temperature to the respective melt point of the phase in relation to the reference LWR fuel UO_2 The impact of the high temperature phase transformation in U_3Si_5 will also be discussed in relation to operating conditions in an LWR Finally, an overview of remaining challenges that exist in the U-S_1 system will be presented.
机译:由于这些化合物的高热导率和假定的氧化耐受性,近年来对铀硅化物二元铀的研究得到了更新,可用于轻水反应堆事故容忍的燃料概念。提高的热导率会降低径向燃料的温度曲线,从而降低燃料的径向温度。系统中观察到的热应力然而,对二元U-Si化合物的研究历来集中在高裂变密度化合物U3S1和U_3Si_2上,以支持RERTR运动。这些研究的性质和微观结构具有很大的可变性,因此需要完整的重新评估是否要考虑将这些燃料用于进一步的辐射测试LANL的实验强调制造近似化学计量的,低氧杂质含量的U3S1,U_3Si_2,US_1和U_3Si_5标本以进行热物理性质和氧化测试,以帮助建模和仿真社区准确地进行数据预测这些新型燃料将在堆中发挥作用。但是,系统中仍存在许多未知数。只有极少数的U-Si化合物经过了辐照测试,显示出一定程度的非晶化和不规则的孔形,从而使得膨胀行为难以预测。裂变产物硅化物在热力学和物理性质方面的文献描述也有限。特性同样,在文献中也忽略了USi_(2-x)附近的相变和相稳定性随温度变化的影响。本文将研究U-Si化合物的最新特性,该特性是温度相对于参考LWR燃料UO_2相对于相的各自熔点的函数。还将讨论U_3Si_5中高温相变的影响与轻水堆中的运行条件相关的问题最后,将概述U-S_1系统中仍然存在的挑战。

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