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Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library
Science and Technology of Nuclear Installations ( IF 1.0 ) Pub Date : 2021-04-15 , DOI: 10.1155/2021/8838097
Sonia M. Reda 1 , Ibrahim M. Gomaa 2 , Ibrahim I. Bashter 1 , Esmat A. Amin 3
Affiliation  

In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER-1000 reactor was discussed. The reference core was initially filled with enriched uranium oxide fuel and then fueled with uranium-thorium fuel. The calculations determine the delayed neutron fraction βeff, the temperature reactivity coefficients, the fuel consumption, and the production of the transuranic elements during reactor operation. βeff and the Doppler coefficient (DC) are found to be in agreement with the design values. It is found that the core loaded with uranium and thorium has lower delayed neutron fraction than the uranium oxide core. The moderator temperature coefficients of the uranium-thorium core are found to be higher than those of the uranium core. Results indicated that thorium has lower production of minor actinides (MAs) and transuranic elements (mainly plutonium isotopes) compared with the relatively large amounts produced from the uranium-based fuel UO2.

中文翻译:

使用带有ENDF库的Thor燃料的VVER-1000反应堆的中子性能

在本文中,使用MCNP6代码以及ENDF / B-VII.1和ENDF / B-VIII库对VVER-1000反应堆进行了中子学计算和核心分析。讨论了introduction的引入对VVER-1000反应堆中子学参数的影响。参考堆芯最初填充了浓缩的氧化铀燃料,然后填充了铀-fuel燃料。计算确定的缓发中子分数β EFF,温度反应性系数,燃料消耗,以及生产在反应堆运行期间的超铀元素。β有效发现多普勒系数(DC)与设计值一致。发现载有铀和th的堆芯具有比氧化铀核更低的延迟中子分数。发现铀-core核的慢化温度系数高于铀核的温度系数。结果表明,与由铀基燃料UO 2产生的相对大量的th相比,th的次要act系元素(MAs)和超铀元素(主要是p同位素)的产生较低。
更新日期:2021-04-15
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