| Issue |
EPJ Web Conf.
Volume 302, 2024
Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2024)
|
|
|---|---|---|
| Article Number | 05001 | |
| Number of page(s) | 10 | |
| Section | Multi-Physics Simulations | |
| DOI | https://doi.org/10.1051/epjconf/202430205001 | |
| Published online | 15 October 2024 | |
https://doi.org/10.1051/epjconf/202430205001
Neutronics and thermal hydraulics analysis on a Lead-bismuth-cooled fast reactor
1 State Power Investment Corporation Research Institute, 102209 Beijing, China
2 Sun Yat-sen University, 519082 Zhuhai, China
* Corresponding author: ffrogchen@163.com
Published online: 15 October 2024
Breeding Lead-base Economical Safe System-Demonstration BLESS-D is a lead-bismuth-cooled fast reactor proposed by China State Power Investment Corporation Research Institute. It features a pool-type configuration of pressure vessel with a thermal/electric power of 300/100 MW. Neutronics and thermal hydraulics analysis are performed, mainly including a sensitivity study of the fuel components, fuel enrichment, and control-assembly arrangement on the lifetime, and the temperature filed for the fuel assembly with the largest thermal power. The results show that compared with PWR, the 239Pu production for BLESS-D is significantly higher, and the quantity of MAs is also reduced, while the productions of LLFPs are at the same scale. It has also been found that under steady state conditions, the largest temperatures of the fuel pellet, cladding and coolant are all below relevant criteria, showing a good performance in the thermal hydraulics for the design. Optimizing the fuel loading scheme for achieving a safer performance would be a part of the future’s work.
© The Authors, published by EDP Sciences, 2024
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