加强临界计算中典型二氧化铀燃料的有效温度模型

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tianxiang Wang , Changyou Zhao , Jun Lin , Shengli Chen , Mingtao He , Hao Chen , Hao Yang , Zhuo Li
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引用次数: 0

摘要

在当前的中子输运方程计算中,一种提高计算效率的常用策略是将燃料温度分布近似为均匀分布。这种方法定义了一个均匀温度,称为有效温度(Teff),它可以保持模型与实际温度梯度相对应的反应性。根据 AFA-3G 燃料二氧化铀球团内部的实际温度分布,本研究引入了体积平均温度的加权系数,以扩展 Chabert-Santamarina 模型。这一扩展模型是罗兰兹模型和 Chabert-Santamarina 模型的一般化表述,在偏差波动和中心值方面比目前的五个有效温度模型表现出更优越的性能。这一结论通过独立模拟得到了验证,OpenMC 采用了窗口多极(WMP)数据库,而 RMC 则利用了点向 ACE 库或高斯-赫米特正交得出的在线多普勒展宽数据。因此,本改进的有效模型提高了有效温度和由此产生的反应性的准确性。此外,在整个组件中使用统一有效温度的偏差仍在可接受的不确定性范围内(3 σ)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Enhancing the effective temperature model for typical UO2 fuel in criticality calculations
In current neutron transport equation calculations, a common strategy to enhance computational efficiency is approximating the fuel temperature distribution as uniform. This approach defines a uniform temperature, known as the effective temperature (Teff), which preserves the reactivity of the model corresponding to the actual temperature gradient. Based on the actual temperature distributions within the UO2 pellet of the AFA-3G fuel, the present study introduces a weighting coefficient for the volume-averaged temperature to extend the Chabert-Santamarina model. This extended model, as a generalized formulation of both the Rowlands and Chabert-Santamarina models, demonstrates superior performance to the current five effective temperature models in terms of deviation fluctuation and central values. This conclusion is verified through independent simulations, with OpenMC employing the Windowed Multi-Pole (WMP) database and RMC utilizing point-wise ACE library or data derived from Gaussian-Hermite quadrature for online Doppler broadening. Therefore, the present refined effective model enhances the accuracy of effective temperature and the resulting reactivity. Furthermore, the deviation of using a uniform effective temperature across the assembly remains within the acceptable uncertainty range (3 σ).
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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