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Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-09-01 , DOI: 10.1016/j.anucene.2020.107590
M. Alqahtani , A. Buijs , S.E. Day

Abstract The tracking of fuel inventory is important for safety and for knowledge of the flux distribution. In a research reactor, tracking of the reactor core fuel composition using simulation code is crucial for fuel management strategy, such as by optimizing the core pattern for sample irradiation purposes and for providing an economical fuel cycle length. Operational data history for the McMaster Nuclear Reactor (MNR) is a valuable asset for comparing and validating simulation code. A previous study examined U-235 content using the nodal diffusion code Overall System for CAlculation of Reactors (OSCAR-4) against standard MNR operational data and recommended considering the Pu-239 content in the energy production in the standard operational data. In this work, a new method was implemented by introducing a Fuel Inventory Correction (FIC) factor for improving the U-235 operational data records. U-238 and Pu-239 code-to-code tracking comparisons were also employed. The maximum difference between U-235 at end of life (EOL) and the updated operational data history was 2.43% and 6.97% for Serpent 2 and OSCAR-4, respectively. The FA power profile tracking showed a similar response whenever fuel shuffling and/or refueling occurred, with a maximum different of 16% (30 kW) in one cycle. The multiplication factors for the two sets of code differed systematically, averaging 0.9982 and 1.0051 for Serpent 2 and OSCAR-4, respectively.

中文翻译:

与麦克马斯特核反应堆相比,Serpent-2 和 OSCAR-4 计算工具改进了 U-235 燃料库存跟踪、本地功率跟踪和倍增因子验证的运行数据历史记录

摘要 燃料库存的跟踪对于安全和了解流量分布很重要。在研究堆中,使用模拟代码跟踪反应堆堆芯燃料成分对于燃料管理策略至关重要,例如通过优化堆芯模式以实现样品辐照目的和提供经济的燃料循环长度。麦克马斯特核反应堆 (MNR) 的运行数据历史是比较和验证仿真代码的宝贵资产。之前的一项研究使用节点扩散代码整体计算反应堆系统 (OSCAR-4) 对照标准 MNR 运行数据检查了 U-235 含量,并建议在标准运行数据中考虑能源生产中的 Pu-239 含量。在这项工作中,通过引入燃料库存校正 (FIC) 因子来实施一种新方法,以改进 U-235 操作数据记录。还采用了 U-238 和 Pu-239 代码到代码跟踪比较。对于 Serpent 2 和 OSCAR-4,U-235 报废 (EOL) 与更新的运营数据历史之间的最大差异分别为 2.43% 和 6.97%。FA 功率曲线跟踪显示出类似的响应,无论何时发生燃料改组和/或加油,在一个循环中最大差异为 16% (30 kW)。两组代码的乘法系数系统地不同,Serpent 2 和 OSCAR-4 的平均系数分别为 0.9982 和 1.0051。对于 Serpent 2 和 OSCAR-4,U-235 报废 (EOL) 与更新的运营数据历史之间的最大差异分别为 2.43% 和 6.97%。FA 功率曲线跟踪显示出类似的响应,无论何时发生燃料改组和/或加油,在一个循环中最大差异为 16% (30 kW)。两组代码的乘法系数系统地不同,Serpent 2 和 OSCAR-4 的平均系数分别为 0.9982 和 1.0051。对于 Serpent 2 和 OSCAR-4,U-235 报废 (EOL) 与更新的运营数据历史之间的最大差异分别为 2.43% 和 6.97%。FA 功率曲线跟踪显示出类似的响应,无论何时发生燃料改组和/或加油,在一个循环中最大差异为 16% (30 kW)。两组代码的乘法系数系统地不同,Serpent 2 和 OSCAR-4 的平均系数分别为 0.9982 和 1.0051。
更新日期:2020-09-01
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