Potentialities of the fast spectrum molten salt reactor concept: REBUS-3700

• Published in: Energy conversion and management Vol. 47; no. 17; pp. 2761 - 2771
• Main Authors: Mourogov, A., Bokov, P.M.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Oxford Elsevier Ltd 01-10-2006; Elsevier
• Subjects: Applied sciences; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fast reactor; Fission nuclear power plants; Installations for energy generation and conversion: thermal and electrical energy; Molten salt fuel; Safety analysis; Fast reactor; Molten salt fuel; Safety analysis; Uranium chloride; Actinide Chlorides; Sodium chloride; Reprocessing; Research and development; Nuclear reactor; Molten salt; Salt; Fuel; Plutonium chlorides
• ISSN: 0196-8904; 1879-2227
• DOI: 10.1016/j.enconman.2006.02.013

The work is realized in the frame of EDF R&D project devoted to innovative nuclear systems. This paper deals with the characteristics of fast reactor REBUS-3700 using molten salt fuel consisting of uranium and transuranics trichlorides dissolved in sodium chloride. A description of the system design, as well as a justification of its operating parameters is given. The performed neutronics studies demonstrate that REBUS-3700 gathers a positive breeding gain and strong negative salt expansion reactivity feedback. The safety analysis demonstrates an excellent reactor behavior with respect to the majority of single and combined unprotected events. The work also reveals the necessity to get more accurate nuclear data for the chlorine isotopes and to investigate the reactor configuration with radial fertile blanket. It seems also indispensable to realize more detailed thermo-hydraulic calculations and especially to perform a sizeable R&D program on structure material capable to resist the corrosion induced by chlorides.