The Molten Salt Reactor (MSR) represents an old concept, but its properties are qualifying it for the advanced utilization: inherent safety, excellent neutron economy, possibility of continuous or batch reprocessing without fuel fabrication. The aim of this paper is to characterize the MSR unique fuel cycle advantages in different neutron spectra using the results of ERANOS-based EQL3D and ECCO-MATLAB based EQL0D procedures. It also focuses on the low production of higher actinides in the Th-U cycle and based on the results, it proposes a simplified in situ recycling of the fuel and the delayed ex situ carrier salt cleaning or direct disposal by vitrification.
- Nuclear Engineering Division
Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning
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Křepel, J, Bykov, V, Mikityuk, K, Hombourger, B, Fiorina, C, & Pautz, A. "Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T05A015. ASME. https://doi.org/10.1115/ICONE22-30396
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