Open Access
Advanced liquid-metal thermal hydraulics research for MyRRHA
K. K. Van Tichelen,Graham Kennedy,Fabio Mirelli,Alessandro Marino,A. Toti,D. Rozzia,E. Cascioli,S. Keijers,Philippe Planquart +8 more
- pp 1-16
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TLDR
The Belgian Nuclear Research Centre (SCK•CEN) is at the forefront of heavy liquid-metal (HLM) nuclear technology worldwide with the development of the Multi-purpose hYbrid Research Reactor for High...Abstract:
The Belgian Nuclear Research Centre (SCK•CEN) is at the forefront of heavy liquid-metal (HLM) nuclear technology worldwide with the development of the Multi-purpose hYbrid Research Reactor for High...read more
References
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Journal ArticleDOI
Design and R&D Progress of China Lead-Based Reactor for ADS Research Facility
TL;DR: In 2011, the Chinese Academy of Sciences launched an engineering project to develop an accelerator-driven subcritical system (ADS) for nuclear waste transmutation as mentioned in this paper, which was selected as the reference reactor for ADS development, as well as for the technology development of the Generation IV lead-cooled fast reactor.
Journal ArticleDOI
Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers
TL;DR: In this paper, a 19-pin hexagonal rod bundle with wire spacers, cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory (KALLA).
Journal ArticleDOI
Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly
Elia Merzari,Paul Fischer,Haomin Yuan,K. Van Tichelen,S. Keijers,J. De Ridder,Joris Degroote,Jan Vierendeels,H. Doolaard,V.R. Gopala,Ferry Roelofs +10 more
TL;DR: In this paper, the authors compare the results obtained by the different participants with the reference Nek5000 results, especially for the cross-flow data, and highlight issues with current modeling approaches, which is intended both to serve as a surrogate for physical experiments and to provide insight into experimental results.
Journal ArticleDOI
Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility
TL;DR: The NACIE-UP experimental facility at the ENEA Brasimone Research Centre (Italy) allowed to evaluate the heat transfer coefficient of a wire-spaced fuel bundle cooled by lead-bismuth eutectic (LBE) as mentioned in this paper.
Journal ArticleDOI
Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors
TL;DR: In this paper, the main features of typical lead-based fast reactors (LFRs) worldwide are reviewed and current challenges in their development are pointed out, including the flow and heat transfer characteristics of the coolant, thermal-hydraulic analysis of the reactor core, lead pool and reactor system.