Transient analyses for a molten salt fast reactor with optimized core geometry

Abstract : Molten salt reactors (MSRs) have encountered a marked resurgence of interest over the past decades, highlighted by their inclusion as one of the six candidate reactors of the Generation IV advanced nuclear power systems. The present work is carried out in the framework of the European FP-7 project EVOL (Evaluation and Viability Of Liquid fuel fast reactor system). One of the project tasks is to report on safety analyses: calculations of reactor transients using various numerical codes for the molten salt fast reactor (MSFR) under different boundary conditions, assumptions, and for different selected scenarios. Based on the original reference core geometry, an optimized geometry was proposed by Rouch et al. (2014. Ann. Nucl. Energy 64, 449) on thermal-hydraulic design aspects to avoid a recirculation zone near the blanket which accumulates heat and very high temperature exceeding the salt boiling point. Using both fully neutronics thermal-hydraulic coupled codes (SIMMER and COUPLE), we also re-confirm the efforts step by step toward a core geometry without the recirculation zone in particular as concerns the modifications of the core geometrical shape. Different transients namely Unprotected Loss of Heat Sink (ULOHS), Unprotected Loss of Flow (ULOF), Unprotected Transient Over Power (UTOP), Fuel Salt Over Cooling (FSOC) are intensively investigated and discussed with the optimized core geometry. It is demonstrated that due to inherent negative feedbacks, an MSFR plant has a high safety potential.
Document type :
Journal articles
Complete list of metadatas

http://hal.in2p3.fr/in2p3-01214779
Contributor : Emmanuelle Vernay <>
Submitted on : Tuesday, October 13, 2015 - 9:34:20 AM
Last modification on : Tuesday, May 22, 2018 - 9:48:10 PM

Identifiers

Collections

IN2P3 | LPSC | UGA

Citation

R. Li, S. Wang, A. Rineiski, D. Zhang, E. Merle-Lucotte. Transient analyses for a molten salt fast reactor with optimized core geometry. Nuclear Engineering and Design, Elsevier, 2015, 292, pp.164-176. ⟨10.1016/j.nucengdes.2015.06.011⟩. ⟨in2p3-01214779⟩

Share

Metrics

Record views

104