Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-09-28 DOI:10.1016/j.nucengdes.2024.113602

G. Zullo , A. Scolaro , T. Barani , D. Pizzocri

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Abstract

In this work, we propose a modelling approach for the intra-granular fission gas behaviour in UO₂ under restructuring process. Leveraging the definition of restructured volume fraction, we consider the fuel matrix transition from the non-restructured to the restructured phase, together with the evolution of the corresponding fission gas concentrations retained in the fuel matrix. Firstly, we derive a sweeping term that exchanges fission gas atoms from the non-restructured to the restructured fuel region. The sweeping term is then included in the conventional intra-granular fission gas diffusion problem. Secondly, the spectral diffusion algorithm is employed to solve two spatially-dimensionless problems, properly representing the non-restructured region with micrometric grains and the restructured region with sub-micrometric grains. The model developed is implemented in SCIANTIX, a 0D meso-scale code for physics-based modelling of fission gas behaviour in nuclear oxide fuel and compared with experimental data and semi-empirical models.

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重组氧化物核燃料中裂变气体扫除的两相模型

在这项工作中，我们提出了一种在重组过程中二氧化铀晶内裂变气体行为的建模方法。利用重组体积分数的定义，我们考虑了燃料基质从非重组阶段到重组阶段的转变，以及燃料基质中保留的相应裂变气体浓度的演变。首先，我们推导出一个扫描项，用于将裂变气体原子从非重组燃料区交换到重组燃料区。然后，在传统的粒内裂变气体扩散问题中加入扫频项。其次，采用光谱扩散算法来解决两个无空间维度的问题，分别恰当地表示具有微米级晶粒的非重组区域和具有亚微米级晶粒的重组区域。所开发的模型在 SCIANTIX 中实施，SCIANTIX 是一种 0D 中尺度代码，用于对核氧化物燃料中的裂变气体行为进行物理建模，并与实验数据和半经验模型进行比较。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.