Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code

M. Hossain, Y. Akter, Mehraz Zaman Fardin, A. S. Mollah
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引用次数: 1

Abstract

A handful of computational benchmarks that incorporate VVER-1000 assemblies having low enriched uranium (LEU) and the mixed oxide (MOX) fuel have been put forward by many experts across the world from the Nuclear Energy Agency. To study & scrutinize the characteristics of one of the VVER-1000 LEU & MOX assembly benchmarks in different states were considered. In this work, the VVER-1000 LEU and MOX Assembly computational-benchmark exercises are performed using the OpenMC software. The work was intended to test the preciseness of the OpenMC Monte Carlo code using nuclear data library ENDF/B-VII.1, against a handful of previously obtained solutions with other computer codes. The kinf value obtained was compared with the SERPENT and MCNP result, which presented a very good similarity with very few deviations. The kinf variation with respect to burnup upto 40 MWd/kgHM was obtained for State-5 by using OpenMC code for both the LEU and MOX fuel assembly. The depletion curves of isotope concentrations against burnup upto 40 MWd/kg/HM were also generated for both the LEU and MOX fuel assembly. The OpenMC results are comparable with those of benchmark mean values. The neutron energy vs flux spectrum was also generated by using OpenMC code. Based on the OpenMC results such as kinf, burnup, isotope concentrations and neutron energy spectrum, it is concluded that the OPenMC code with ENDF/B-VII.1 nuclear data library was successfully implemented. It is planned to use OpenMC code for calculation of neutronics and burnup of the VVER-1200 reactor to be commissioned in Bangladesh by 2023/2024.
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Neutronics和使用OpenMC代码的VVER-1000 LEU和MOX汇编计算基准的燃耗分析
世界各国核能机构的许多专家已经提出了一些计算基准,这些基准包括使用低浓缩铀(LEU)和混合氧化物(MOX)燃料的VVER-1000组件。为了研究和仔细检查不同州的VVER-1000低浓铀和MOX组件基准之一的特性。在这项工作中,使用OpenMC软件进行了VVER-1000 LEU和MOX Assembly计算基准练习。该工作旨在使用核数据库ENDF/B-VII测试OpenMC蒙特卡罗代码的准确性。1、用其他计算机代码与先前获得的少数解进行比较。将得到的kinf值与SERPENT和MCNP结果进行比较,两者具有很好的相似性,偏差很小。通过使用OpenMC代码对低浓铀和MOX燃料组件进行计算,得到了State-5燃耗高达40 MWd/kgHM时的kinf变化。得到了低浓缩铀和MOX燃料组件在燃耗高达40 MWd/kg/HM时的同位素浓度耗尽曲线。OpenMC结果与基准平均值具有可比性。利用OpenMC程序生成了中子能量通量谱。根据OpenMC的kinf、燃耗、同位素浓度和中子能谱等结果,得出OpenMC代码符合ENDF/B-VII的结论。1个核数据库成功实施。计划使用OpenMC代码计算将于2023/2024年在孟加拉国投入使用的VVER-1200反应堆的中子和燃料量。
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