Abstract
This study aims to provide a thorough analysis of corium-fragmentation characteristics under sodium-cooled fast reactor (SFR) severe accidents, with a special emphasis on quantitatively evaluating the properties of generated fuel fragments. A visualized thermo-hydraulic characteristics in a melt coolant interaction-II apparatus is designed and built, and an array of simulative tests are conducted by discharging a fused stainless-steel jet into the coolant. Quantitative data, including the agglomerate mass fraction, fragment-size distribution, fragment mean diameter, particle-bed porosity, and granule sphericity, are obtained, and the influences of melt temperature, water temperature, melt-penetration speed, melt mass, and water depth on the fragmentation behavior of the fused stainless-steel jet are systematically analyzed in detail. Moreover, we compare the experimental data with theoretical results. These experimental results provide data to support the development and verification of SFR severe-accident analysis codes in China. © The Author(s), under exclusive licence to China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society 2026.
| Original language | English |
|---|---|
| Article number | 162 |
| Number of pages | 25 |
| Journal | Nuclear Science and Techniques |
| Volume | 37 |
| Issue number | 9 |
| Online published | 16 Jun 2026 |
| DOIs | |
| Publication status | Published - Sept 2026 |
Funding
This work was supported by the Fundamental Research Funds for the Central Universities (No. 3072024CFJ1506), the Science and Technology Program of Guangdong Province (No. 2025A0505020037) and the Hainan Provincial Natural Science Foundation of China (No. 526MS0257).
Research Keywords
- Fragmentation behavior
- Fuel-coolant interaction
- Particle bed
- Severe accident
- Sodium-cooled fast reactor
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