The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Online ISSN : 2424-2934
2019.27
Session ID : 1264
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NEUTRONIC EVALUATION OF THE UO2-BEO FUEL BASED ON THE LATTICE PHYISICS CALCULATION
*Qian ZhangXiaomiao ChiYunfei ZhangLiang LiangQiang ZhaoXiang WangXingjian Wen
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Abstract

Using an in-house deterministic lattice physics calculation code, the enhanced thermal conductivity fuel concept of the UO2-BeO fuel is analyzed on the pin and lattice level. Due to the neutron absorption effect and the moderating effect brought by BeO, impact on the reactivity caused by different BeO volume fraction is investigated. Results show that increase of enrichment is necessary to maintain the overall reactivity provided by fuel lattice for the entire fuel cycle. The neutronic features of the UO2-BeO fuel during depletion is investigated that adding BeO leads to reduce on 239Pu production. In addition, the reactivity coefficient of the UO2- BeO fuel is preliminarily investigated and it is noteworthy that increasing BeO volume fraction will lead to less negative reactivity feedback.

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© 2019 The Japan Society of Mechanical Engineers
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