首页> 外文期刊>Nuclear science and engineering >A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments
【24h】

A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments

机译:基于IFA-597实验的MOX燃料销传热的验证研究

获取原文
获取原文并翻译 | 示例
       

摘要

The IFA-597 (Integrated Fuel Assessment) experiments from the International Fuel Performance Experiments database were designed to study the thermal behavior of mixed oxide (MOX) fuel and the effects of an annulus on fission gas release in light water reactor fuel. An evaluation of nuclear fuel pin heat transfer in the FRAPCON-3.4 and Exnihilo codes for MOX fuel systems was performed, with a focus on the first 20 time steps (~6 GWd/tonne initial heavy metal) for explicit comparison between the codes. In addition, sensitivity studies were performed to evaluate the effect of the radial power shape and approximations to the geometry to account for the thermocouple hole, dish, and chamfer. The analysis demonstrated relative agreement for both solid (rod 1) and annular (rod 2) fuel in the experiment, demonstrating the accuracy of the codes and their underlying material models for MOX fuel, while also revealing a small energy loss artifact in how gap conductance is currently handled in Exnihilo for chamfered fuel pellets. The within-pellet power shape was shown to impact the predicted centerline temperatures significantly. This has provided an initial benchmarking of the pin heat transfer capability of Exnihilo for MOX fuel with respect to a well-validated nuclear fuel performance code. This analysis was done for a heavy-water boiling water reactor, but the conclusions are not limited by the reactor type beyond the spectrum and particular materials.
机译:来自国际燃料性能实验数据库的IFA-597(综合燃料评估)实验旨在研究混合氧化物(MOX)燃料的热行为以及环形空间对轻水反应堆燃料中裂变气体释放的影响。对FRAPCON-3.4和MONI燃料系统的Exnihilo代码中的核燃料销传热进行了评估,重点是前20个时间步长(约6 GWd /吨初始重金属),以明确比较这些代码。此外,还进行了敏感性研究,以评估径向功率形状及其对几何形状的近似影响,以说明热电偶孔,碟和倒角。分析表明实验中固体(棒1)和环形(棒2)燃料都相对一致,证明了MOX燃料的代码及其底层材料模型的准确性,同时还揭示了间隙电导如何产生较小的能量损失伪像目前在Exnihilo加工倒角的燃料颗粒。丸内功率形状显示出显着影响预测的中心线温度。相对于经过充分验证的核燃料性能代码,这为Exnihilo对MOX燃料的销钉传热能力提供了初始基准。该分析是针对重水沸腾反应堆进行的,但结论不受限于光谱和特定材料之外的反应堆类型限制。

著录项

  • 来源
    《Nuclear science and engineering》 |2014年第2期|172-185|共14页
  • 作者单位

    University of Tennessee, Department of Nuclear Engineering 315 Pasqua Engineering Building, Knoxville, Tennessee 37996;

    University of Tennessee, Department of Nuclear Engineering 315 Pasqua Engineering Building, Knoxville, Tennessee 37996;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

    Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6170;

  • 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
  • 关键词

  • 入库时间 2022-08-18 00:42:57

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号