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Burnup and neutronic analysis for UOX and MOX fuel assemblies in VVER reactor
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2021-07-31 , DOI: 10.1016/j.anucene.2021.108586
Heba K. Louis 1 , Esmat Amin 1
Affiliation  

The present work examined the feasibility of utilizing Mixed Uranium–Plutonium Oxide (MOX) fuel in the VVER-1000 reactor core. In this study, about 30% of Uranium Oxide (UOX) fuel assemblies of the original core are replaced by MOX fuel assemblies. The effect of MOX fuel on the safety parameters is studied by using the MCNP6 code and the nuclear data library (ENDF/B)-VII.1. The safety parameters examined included the effective multiplication factor, temperature coefficients, void coefficient, boron coefficient, shutdown margin and the kinetic parameters. The excess reactivity, neutron flux and power density distributions and power peaking factor are also examined. All estimated values of reactivity coefficients analyzed for the core contains 30% MOX fuel confirmed to be negative, which guarantees the reactor safety and power stability in a normal state. Also, the effective delayed neutron fraction was lower than that of the full UOX core as well as the neutron lifetime was shorter, this shows that the MOX core responds faster than the UOX core. The maximum power factor for the MOX core was equal to the design limit. The shutdown margin satisfied the design requirement. The results confirmed that the VVER-1000 is able to meet the safety requirement for core designs with MOX loadings of up to 30%.



中文翻译:

VVER 反应堆中 UOX 和 MOX 燃料组件的燃耗和中子分析

目前的工作研究了在 VVER-1000 反应堆堆芯中使用混合铀钚氧化物 (MOX) 燃料的可行性。在这项研究中,原始堆芯中约 30% 的氧化铀 (UOX) 燃料组件被 MOX 燃料组件取代。利用MCNP6代码和核数据库(ENDF/B)-VII.1研究了MOX燃料对安全参数的影响。检查的安全参数包括有效倍增系数、温度系数、空隙系数、硼系数、关闭裕度和动力学参数。还检查了过量反应性、中子通量和功率密度分布以及功率峰值因数。为堆芯分析的所有反应系数估计值包含 30% MOX 燃料,确认为负值,保证了反应堆在正常状态下的安全性和功率稳定性。此外,有效延迟中子分数低于完整的 UOX 核心,中子寿命更短,这表明 MOX 核心比 UOX 核心响应更快。MOX 磁芯的最大功率因数等于设计极限。关断裕度满足设计要求。结果证实,VVER-1000 能够满足 MOX 负载高达 30% 的堆芯设计的安全要求。

更新日期:2021-08-01
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