燃料性能代码与 OECD/NEA MPCMIV 基准代码的比较分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-11-13 DOI:10.1016/j.nucengdes.2024.113685

Quentin Faure , Gregory Delipei , Alessandro Scolaro , Maria Avramova , Kostadin Ivanov

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引用次数: 0

摘要

最近开发的多物理场颗粒包层机械相互作用验证（MPCMIV）基准包括专门的瞬态燃料性能练习。在这项工作中，使用了三种燃料性能代码（BISON、OFFBEAT、FAST）为基准进行辅助研究。演习包括在沸水反应堆中对父棒进行为期三年的基本辐照，然后对从父棒改制的小燃料棒进行冷斜坡瞬态辐照。与测量结果相比，基础辐照的结果令人满意，OFFBEAT 和 BISON 在包壳外径方面发现了一些差异，这可以用这两种代码中实施的氧化模型来解释。冷斜坡包括非常快速的功率增加，线性热率在几秒钟内从零增加到最大值，关于冷斜坡，所有代码都倾向于低估包层轴向伸长的时间演变。在包层轴向伸长时间演化的最大振幅和形状方面，都观察到了预测值与测量值之间的差异。这表明对现象的预测并不准确。利用多物理场耦合（Griffin、BISON、THM），涉及反应堆物理、热-液压和燃料性能，对斜坡进行了研究，并获得了 LHR 的估计值。然后根据新的 LHR 更新 OFFBEAT 模型。与测量结果相比，包壳轴向伸长率的预测结果具有更好的一致性。在单一物理燃料性能建模中，线性热率是通过量热技术获得的，不适合快速瞬态；而在多物理模型中，线性热率是由多物理模型预测的，然后作为燃料性能代码中的源项。进一步分析获得的结果，在包层的一小部分观察到了塑性应变，主要是轴向应变，振幅比峰值瞬态时的总应变低一个数量级。今后的工作重点是通过实施摩擦接触来改进 BISON 模型，并将该模型用于更多的多物理场研究。

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Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark

The recently developed Multi-Physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) benchmark includes dedicated transient fuel performance exercises. In this work, three fuel performance codes (BISON, OFFBEAT, FAST) are used to perform supporting studies for the benchmark. The exercises consist of a three-year long base irradiation of a father rod in a boiling water reactor followed by a cold ramp transient for a fuel rodlet refabricated from the father rod. For the base irradiation, the results obtained are satisfactory in comparison to the measurements, with some discrepancies observed in the cladding outer diameter for OFFBEAT and BISON, which can be explained by the oxidation models implemented in both codes. Concerning the cold ramp, which consists of a very fast power increase with the linear heat rate going from zero to its maximal value in just a few seconds, all the codes tend to underpredict the cladding axial elongation temporal evolution. The observed discrepancies between predictions and measurements are both in the maximal amplitude and shape of the cladding axial elongation temporal evolution. This suggests that the phenomenology is not predicted accurately. Using a multi-physics coupling (Griffin, BISON, THM), involving reactor-physics, thermal–hydraulic, and fuel performance, the ramp is investigated and an estimation of the LHR is obtained. The OFFBEAT model is then updated with the new LHR. The cladding axial elongation is predicted with significant better agreement compared to the measurements. In single physics fuel performance modeling, the linear heat rate is obtained by calorimetric technique, which is not suited for fast transient, while in the multi-physics model, the linear heat rate is predicted instead by the multi-physics model and then is used as a source term in the fuel performance code. Analyzing further the obtained results, plastic strains mainly axially and with an amplitude one order of magnitude lower than the total strain at peak transient are observed on a small part of the cladding. Future work will focus on improving the BISON model by implementing frictional contact and to use the model for more multi-physics studies as well.

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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.