To: TobagoJack who wrote (152707 ) 1/30/2020 9:43:23 AM From: Haim R. Branisteanu Respond to of 217543 Will it work by July of this year? Research on molten salt coolant has been revived at Oak Ridge National Laboratory ORNL) in the USA with the Advanced High-Temperature Reactor (AHTR). 16 This is a larger reactor using a coated-particle graphite-matrix TRISO fuel like that in the GT-MHR (see above section on the GT-MHR ) and with molten fluoride (FLiBe) salt as primary coolant. While similar to the gas-cooled HTR it operates at low pressure (less than 1 atmosphere) and higher temperature, and gives better heat transfer than helium. The FLiBe salt is used solely as primary coolant, and achieves temperatures of 750-1000°C or more while at low pressure. This could be used in thermochemical hydrogen manufacture. A 5 MW thorium-fuelled prototype is under construction at Shanghai Institute of Nuclear Applied Physics (SINAP, under the China Academy of Sciences) originally with 2015 target for operation, now 2020. This is also known as the fluoride salt-cooled high-temperature reactor (FHR). A 100 MWt demonstration pebble-bed plant with open fuel cycle is planned by about 2025. SINAP sees this design having potential for higher temperatures than MSRs with fuel salt. A small version of the AHTR/FHR is the SmAHTR, with 125 MWt thermal size matched to early process heat markets, or producing 50+ MWe. Operating temperature is 700°C with FLiBe primary coolant and three integral heat exchangers. It is truck transportable, being 9m long and 3.5m diameter. Fuel is 19.75% enriched uranium in TRISO particles in graphite blocks or fuel plates. Refuelling interval is 2.5 to 4 years depending on fuel configuration. Secondary coolant is FLiNaK to Brayton cycle, and for passive decay heat removal, separate auxiliary loops go to air-cooled radiators. Later versions are intended to reach 850° to 1000°C, using materials yet to be developed. In the USA a consortium including UC Berkeley, ORNL and Westinghouse is designing a 100 MWe pebble-bed FHR , with annular core. It is designed for modular construction, and from 100 MWe base-load it is able to deliver 240 MWe with gas co-firing for peak loads. Fuel pebbles are 30 mm diameter, much less than gas-cooled HTRs. The PB-FHR has negative void reactivity and passive decay heat removal. Reactor sizes of 1500 MWe/3600 MWt are envisaged, with capital costs estimated at less than $1000/kW.