Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, February, 2021 === Cataloged from the official PDF version of thesis. === Includes bibliographical references (pages 319-333). === Advanced reactor concepts which use a lithium- or beryllium-bearing...
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| Format: | Others |
| Language: | English |
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Massachusetts Institute of Technology
2021
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| Online Access: | https://hdl.handle.net/1721.1/131004 |