Very high temperature reactor

Hydrogen Production with Very High-Temperature Reactor.147... 

Hydrogen Production with Very High-Temperature Reactor 4.4.1 Overview of the Very High-Temperature Reactor... 

Furthermore, industrial prospects for high temperature electrochemical or thermochemical processes and the temperature involved, together with non-hydrogen related applications of process heat, will impact the development strategy of high or very high temperature reactors. 

Its heat requirements are well matched to the temperatures available from a Generation IV very/high temperature reactor. 

Furthermore, HEEP will consider several reactor concepts including water reactors such as PWR and PHWR for the lower temperature range, the very high temperature reactors (VHTR), fast breeder reactors (FBR) and molten-salt cooled reactors for the high temperature range, and super-critical water reactor (SCWR) capable of output temperatures up to around 625°C for the medium range of temperature. 

Figure 1 Very high temperature reactor with hydrogen production system...

Concerning the coupling to a nuclear heat source the S-I process is the most intensively studied thermochemical cycle. Due to the high temperatures (> 800°C) needed for the H2S04 decomposition, the first choice is to combine it with a very high temperature reactor (VHTR). 

Very high temperature reactor (VHTR), a version of the HTGR ... 

Very High Temperature Reactor (VHTR) Survey of Materials Research and Development Needs to Support Early Deployment, INL/EXT-03-004-141, January 31, 2003. 

Ueta S, Aihara J, Yasuda A, Ishibashi H, Takayama T, Sawa K (2008) Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor. J Nucl Mater 376 146-151... 

Refueling Options and Considerations for Liquid-Salt-Cooled Very High-Temperature Reactors... 

Ingersoll, D. T., et al. 2005, Status ofPhysics and Safety Analyses for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR), ORNL/TM-2005/218, Oak Ridge National Laboratory,... 

This appendix provides a brief description of the Fast Flux Test Facility (FFTF) fuel handling system and its operation as described by Cabell (1980) and in the Fast Flux Test Facility System Design Description (FFTF, 1983). The description is limited to those system features that are potentially relevant to the refueling of a liquid-salt very high-temperature reactor (LS-VHTR). Because the FFTF was designed as a reactor to test fuel, it has additional capabilities and equipment compared with a sodium-cooled fast reactor designed only to produce electricity. 

Historically, helium has been proposed as the coolant of choice for very high-temperature reactors. 

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