Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design
The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented. Attention is focused mainly on the development of fuel assemblies with fuel based on UO 2 + Al, U 3 Si 2 + Al, and U9%Mo + Al for the LVR-15 rese...
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Published in: | Atomic energy (New York, N.Y.) Vol. 129; no. 4; pp. 234 - 236 |
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Main Authors: | , , , , , , |
Format: | Journal Article |
Language: | English |
Published: |
New York
Springer US
01-02-2021
Springer Springer Nature B.V |
Subjects: | |
Online Access: | Get full text |
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Summary: | The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented. Attention is focused mainly on the development of fuel assemblies with fuel based on UO
2
+ Al, U
3
Si
2
+ Al, and U9%Mo + Al for the LVR-15 research reactor (Czech Republic). A design-basis validation is given for IRT-4M fuel assemblies with fuel composition based on UO
2
+ Al and U
3
Si
2
+ Al, IRT-3M fuel assemblies with a fuel composition based on U9%Mo + Al, and IRT-P fuel assemblies with a fuel composition based on U
3
Si
2
+ Al and UO
2
+ Al. In substantiation of the operability and confirmation of the hydraulic characteristics of the IRT-P fuel assembly, which is equipped with 21 fuel rods, manufactured at NZKhK, there are plans to manufacture and conduct hydraulic testing of a full-scale model. |
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ISSN: | 1063-4258 1573-8205 |
DOI: | 10.1007/s10512-021-00740-9 |