A neutronics-fuel coupling model for the simulation of constituent redistribution in U–Zr fuel

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI:10.1016/j.pnucene.2024.105467

Oscar Lastres, Yunlin Xu, Yi Xie

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引用次数: 0

Abstract

Simulating the dynamic redistribution of elements within metallic fuels, such as U–10Zr (wt.%), is a complex challenge in nuclear power research. While existing models can adequately simulate constituent redistribution throughout the fuel pin, they rely heavily on pre-known power history data or power calculated a priori. Furthermore, existing models do not calculate an accurate actinide inventory throughout the fuel pin. This limitation leads to less precise power distribution calculations, which can negatively affect the efficiency and safety of fuel design and performance. This work aims to introduce a new approach to modeling constituent redistribution for U–10Zr (wt.%) fuel by developing a new code called PFPS that accounts for the depletion and diffusion of Zr throughout the fuel pin during burnup through an explicit coupling method. The approach independently calculates the power distribution by coupling with the reactor physics code, Serpent 2, thereby eliminating the need for externally supplied power history data. The main contribution of this study lies in this coupling to obtain a more accurate history of the compositional evolution of U–Zr fuel and its fission products. This procedure can enhance the understanding of constituent redistribution by calculating a more accurate power distribution and lays the foundation for future attempts to simulate the compositional and microstructural evolution of all materials in the fuel.

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用于模拟 U-Zr 燃料中成分再分布的中子-燃料耦合模型

模拟 U-10Zr（重量百分比）等金属燃料内部元素的动态再分布是核电研究中的一项复杂挑战。虽然现有模型可以充分模拟整个燃料针内的成分再分布，但它们在很大程度上依赖于已知的功率历史数据或先验计算的功率。此外，现有模型无法计算整个燃料销的精确锕系元素库存。这种限制导致功率分布计算不够精确，从而对燃料设计和性能的效率和安全性产生负面影响。这项工作旨在通过开发一种名为 PFPS 的新代码，为 U-10Zr （重量百分比）燃料的成分再分布建模引入一种新方法。该方法通过与反应堆物理代码 Serpent 2 的耦合，独立计算功率分布，从而无需外部提供功率历史数据。本研究的主要贡献在于通过这种耦合获得了更准确的 U-Zr 燃料及其裂变产物成分演变史。这一程序可以通过计算更精确的功率分布来加深对成分再分布的理解，并为今后模拟燃料中所有材料的成分和微结构演变奠定基础。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.