Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide
We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core...
Main Authors: | , , , , |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2020-04-01
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Series: | Nuclear Engineering and Technology |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573319303043 |