A characterization method for reprocessed spent nuclear fuel through neutron and gamma-ray multiplicity counting
It is difficult to measure neutrons and gamma rays coming directly from uranium and plutonium atoms in pyroprocessed ingot, which is of great interest to nuclear safeguards. Most neutrons of the ingot are emitted from 244Cm isotope and gamma rays from its fission products. Therefore, it is necessary...
| Main Authors: | , , |
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| 格式: | 文件 |
| 语言: | English |
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Elsevier
2025-03-01
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| 丛编: | Nuclear Engineering and Technology |
| 主题: | |
| 在线阅读: | http://www.sciencedirect.com/science/article/pii/S1738573324004819 |