Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR)
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015. === Cataloged from PDF version of thesis. === Includes bibliographical references (pages 294-305). === The Fluoride Salt-Cooled High-Temperature Reactor (FHR) is a pebble bed nuclear reactor c...
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| Format: | Others |
| Language: | English |
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Massachusetts Institute of Technology
2016
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| Online Access: | http://hdl.handle.net/1721.1/103727 |