Determination of plutonium and uranium content and burnup using six group delayed neutrons
In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2019-07-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573318305977 |