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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
David Weitzel, Youho Lee (Univ of New Mexico), Michael Short (MIT), Michael Laufer (Kairos Power), Sam Sham (ANL)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1176-1182
Much progress has recently been made on Molten Salt Reactor (MSR) technology with the strategic support of the Department of Energy (DOE). However, concerns regarding the structural material’s compatibility with the salt have hampered the detailed design and evaluation of reliability and economics. Existing research also neglects fluid flow when measuring alloy dissolution. FLiBe flow affects species diffusion through the salt and in turn modifies the reaction kinetics at the alloy surface. Without a proper understanding of the flow effects on alloy dissolution, MSR performance assessments will inevitably remain imprecise.
This research entails the construction of a subscale molten salt loop to test the effects of FLiBe flow on the corrosion rate of various alloys. Our test loop will consist of a molten salt pump connected to a bimetallic composite test loop with a sample holder for the tested alloys. The salt temperature and velocity can be varied independently to replicate the varied operating conditions in the MSR and better characterize the effects of FLiBe flow on corrosion. Investigating the effects of salt flow on alloy element dissolution will advance material choice for key reactor components. These findings will enable nuclear engineers to create more detailed and accurate plant designs.