PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-03-05 DOI:10.1016/j.nucengdes.2025.113960

D. Jaramillo-Sierra , M. Stefanowska-Skrodzka , J. Lavarenne , E. Deveaux , E. Brunetto , V. Matocha , A. Magni , K. Sturm , K. Mikityuk , Y. Wang , A. Jiménez-Carrascosa , J. Gado , B. Burger , V. Blanc , V. Dupont , L. Argeles , B. Perrin , G. Michel , A. Scolaro , C. Fiorina , C. Strmensky

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Abstract

This paper presents the results of the first phase of the benchmark exercise in the PuMMA project, aimed at extending the reliability of fuel performance codes for Mixed Oxide (MOX) fuels with high plutonium content. The exercise involved the simulation of three irradiation experiments: (1) CAPRIX (45 % of Pu) carried out in the PHENIX reactor in France, (2) TRABANT1 (45 % of Pu) and (3) TRABANT2 (40 % of Pu) irradiated in the HFR reactor in The Netherlands. Thirteen organizations from nine countries participated, using eight different fuel performance codes. In this phase, besides the fuel specifications, boundary conditions such as linear heat rate, irradiation history, and cladding external temperature were provided. In a “blind” exercise, all codes were free to choose suitable models and correlations for the simulation without access to the experimental results. The main results of the “blind” phase are performed along with a sensitivity analysis to investigate the impact of various uncertainties on measurements, irradiation and input parameters. Significant discrepancies were observed among the different codes, attributed to the use of heterogeneous reference correlations and the absence of suitable models for some MOX-specific phenomena. Finally, insights are offered for the second phase of the benchmark, where the fuel performance codes’ capabilities will be assessed against experimental results from Post-Irradiation Examinations of all three pins.

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PuMMA盲基准：高钚含量MOX燃料在辐照下的性能

本文介绍了PuMMA项目第一阶段基准测试的结果，旨在提高高钚含量混合氧化物（MOX）燃料性能代码的可靠性。演习包括三个辐照实验的模拟：(1)CAPRIX（45%的Pu）在法国的PHENIX反应堆中进行，(2)TRABANT1（45%的Pu）和(3)TRABANT2（40%的Pu）在荷兰的HFR反应堆中进行辐照。来自9个国家的13个组织参与，使用8种不同的燃料性能代码。在这一阶段，除了燃料规格外，还提供了线性热率、辐照历史和包层外部温度等边界条件。在“盲”练习中，所有代码都可以自由选择合适的模型和相关性进行模拟，而无需访问实验结果。“盲”阶段的主要结果与灵敏度分析一起进行，以研究各种不确定性对测量，辐照和输入参数的影响。不同编码之间存在显著差异，这是由于使用了异质参考相关性，以及缺乏针对某些mox特定现象的合适模型。最后，为基准的第二阶段提供了见解，其中燃料性能代码的能力将根据所有三个引脚的辐照后检查的实验结果进行评估。

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

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.