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Validating the BISON fuel performance code to integral LWR experiments

机译:验证BISON燃油性能代码以进行整体LWR实验

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摘要

BISON is a modern finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 2D axisymmetric, or 3D geometries. Code validation is underway and is the subject of this study. A brief overview of BISON's computational framework, governing equations, and general material and behavioral models is provided. BISON code and solution verification procedures are described, followed by a summary of the experimental data used to date for validation of Light Water Reactor (LWR) fuel. Validation comparisons focus on fuel centerline temperature, fission gas release, and rod diameter both before and following fuel-clad mechanical contact. Comparisons for 35 LWR rods are consolidated to provide an overall view of how the code is predicting physical behavior, with a few select validation cases discussed in greater detail. Results demonstrate that ( 1) fuel centerline temperature comparisons through all phases of fuel life are very reasonable with deviations between predictions and experimental data within +/- 10% for early life through high burnup fuel and only slightly out of these bounds for power ramp experiments, ( 2) accuracy in predicting fission gas release appears to be consistent with state-of-the-art modeling and with the involved uncertainties and ( 3) comparison of rod diameter results indicates a tendency to overpredict clad diameter reduction early in life, when clad creepdown dominates, and more significantly overpredict the diameter increase late in life, when fuel expansion controls the mechanical response. Initial rod diameter comparisons are not satisfactory and have led to consideration of additional separate effects experiments to better understand and predict clad and fuel mechanical behavior. Results from this study are being used to define priorities for ongoing code development and validation activities. (C) 2016 Elsevier B.V. All rights reserved.
机译:BISON是基于现代有限元的核燃料性能规范,自2009年以来一直在爱达荷州国家实验室(INL)进行开发。该规范既适用于稳态燃料也适用于瞬态燃料行为,并已用于分析燃料中的多种燃料形式1D球形,2D轴对称或3D几何形状。代码验证正在进行中,是本研究的主题。简要概述了BISON的计算框架,控制方程以及一般的材料和行为模型。描述了BISON代码和解决方案验证程序,然后总结了迄今为止用于验证轻水反应堆(LWR)燃料的实验数据。验证比较的重点是燃料包层机械接触之前和之后的燃料中心线温度,裂变气体释放和杆直径。合并了35个LWR棒的比较,以提供代码如何预测物理行为的整体视图,并详细讨论了一些选择的验证案例。结果表明(1)在燃料寿命的所有阶段进行的燃料中心线温度比较非常合理,对于高燃耗燃料的早期寿命,预测和实验数据之间的偏差在+/- 10%之内,而对于功率斜升实验仅稍稍超出这些界限,(2)预测裂变气体释放的准确度似乎与最新模型一致,并且涉及不确定性;(3)杆径结果的比较表明,在生命早期,过度预测包层直径减小的趋势当燃料膨胀控制机械响应时,包层的蠕变起主导作用,并且更明显地高估了寿命后期直径的增加。最初的活塞杆直径比较并不令人满意,因此需要考虑另外进行单独的效果实验,以更好地理解和预测包层和燃料的机械性能。这项研究的结果用于确定正在进行的代码开发和验证活动的优先级。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第5期|232-244|共13页
  • 作者单位

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA;

    ANATECH Corp, 5435 Oberlin Dr, San Diego, CA 92121 USA;

    ANATECH Corp, 5435 Oberlin Dr, San Diego, CA 92121 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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  • 入库时间 2022-08-18 00:41:47

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