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Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2021-02-19 , DOI: 10.1016/j.anucene.2021.108144
A.Sz. Ványi , B. Babcsány , Z.I. Böröczki , A. Horváth , M. Hursin , M. Szieberth , Sz. Czifrus

This paper describes steady-state reactor physics measurements and calculations that were performed for the Training Reactor of Budapest University of Technology and Economics (BME TR) with the purpose of benchmarking. Based on the available geometry specifications and material compositions a model of BME TR was created with the well-validated, general-purpose Serpent 2 Monte Carlo code. Uncertain parameters (such as fuel density and control rod positions) were adjusted to related measurements. The Serpent 2 model was used for the generation of group constants, examining several homogenization schemes. Models were created in the PARCS diffusion code, the SPNDYN diffusion and SP3 code and the PARTISN discrete ordinates code. Various Monte Carlo and deterministic calculations were performed with the adjusted models and the results were then compared with actual measured data. The calculations and measurements show good agreement, this way the Serpent model was successfully validated, while the deterministic models make a good basis for more complex benchmarks in the future, such as transients with thermal–hydraulic feedback.



中文翻译:

BME训练反应堆的稳态中子测量和综合数值分析

本文介绍了为进行基准测试而对布达佩斯技术经济大学训练堆(BME TR)进行的稳态反应堆物理测量和计算。根据可用的几何规格和材料成分,使用经过充分验证的通用Serpent 2 Monte Carlo代码创建BME TR模型。不确定的参数(例如燃料密度和控制杆位置)已调整为相关测量值。使用Serpent 2模型生成组常数,检查了几种均化方案。在PARCS扩散代码,SPNDYN扩散和SP3代码以及PARTISN离散纵坐标代码中创建了模型。使用调整后的模型进行各种蒙特卡洛和确定性计算,然后将结果与实际测量数据进行比较。计算和测量结果显示出良好的一致性,通过这种方式,Serpent模型得以成功验证,而确定性模型则为将来更复杂的基准(例如带有热-液压反馈的瞬态)奠定了良好的基础。

更新日期:2021-02-19
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