Module Development and Verification for Fuel-pin Cladding Failure of Sodium-cooled Fast Reactor Based on System Code FRTAC
The inherent safety of reactor is emphasized in the design of sodium-cooled fast reactors (SFRs), and the performance analysis of oxide fuel plays a critical role in the safety assessment of SFRs, as fuel swelling and cladding failure are key phenomena occurring during the early stages of core disru...
সংরক্ষণ করুন:
| প্রধান লেখক: | |
|---|---|
| বিন্যাস: | Artigo |
| ভাষা: | Inglês |
| প্রকাশিত: |
Editorial Board of Atomic Energy Science and Technology
2026-03-01
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| মালা: | Yuanzineng kexue jishu |
| বিষয়গুলি: | |
| অনলাইন ব্যবহার করুন: | https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2025.youxian.0444 |
| ট্যাগগুলো: |
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