Thermal-hydraulic Transient Analysis of Benchmark for FFTF LOFWOS Test #13 Based on FR-Sdaso Code
FFTF LOFWOS Test #13 is an unprotected loss of flow test conducted on the FFTF sodium-cooled loop fast reactor in the United States, aimed at demonstrating the inherent safety characteristics of the reactor. To verify advanced neutron science, thermal-hydraulic, and safety analysis programs for sod...
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| Main Author: | |
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| Format: | Article |
| Language: | English |
| Published: |
Editorial Board of Atomic Energy Science and Technology
2024-09-01
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| Series: | Yuanzineng kexue jishu |
| Subjects: | |
| Online Access: | https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0315 |
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