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Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code
Moscow University Physics Bulletin ( IF 0.4 ) Pub Date : 2020-03-17 , DOI: 10.3103/s0027134919060031
Jamal Al Zain , O. El Hajjaji , T. El Bardouni

The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm2 s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.

中文翻译:

使用DRAGON5代码对MNSR研究堆的燃料耗竭进行中子研究

这项工作的目的是研究30千瓦微型中子源反应堆(MNSR)的燃料消耗。在每周5天,每天2小时的运行条件下,中子热通量峰值为1.0E + 12 n / cm 2 s,估计的铁芯寿命为10年(200天)。DRAGON5代码用于在不同的燃耗值下生成燃料组常数和无穷倍数与MNSR反应堆运行时间的关系。使用DRAGON5传输晶格代码计算反应堆堆芯中燃烧的铀和p的量。结果与以前的研究非常吻合。
更新日期:2020-03-17
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