Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant

Abstract

TitleDesign summary of the Mark-I pebble-bed, fluoride salt-cooled, high-temperature reactor commercial power plant Abstract -The University of California, Berkeley (UCB), has developed a preconceptual design for a commercial pebble-bed (PB), fluoride salt-cooled, high-temperature reactor (FHR) (PB-FHR). The baseline design for this Mark-I PB-FHR (Mk1) plant is a 236-MW(thermal) reactor. The Mk1 uses a fluoride salt coolant with solid, coated-particle pebble fuel. The Mk1 design differs from earlier FHR designs because it uses a nuclear air-Brayton combined cycle designed to produce 100 MW(electric) of base-load electricity using a modified General

Exergy analysis of thermal energy storage options with nuclear power plants

“…The analysis was conducted for thermal storage integration with existing and future generation NPPs based on the plant design data from literature (Doster et al, 2012;Ball, 2004;Andreades and Peterson, 2014). The study reveals that there are various possible options to store thermal energy of next generation NPPs efficiently, but the options for existing NPPs are limited.…”

“…The PB-FHR design is a 236 MW (th) reactor system, with a corresponding electrical power rating of 100 MW(e) at the base-load operation. Operating conditions and RC properties are provided in Table 2 for the PB-FHR (Andreades and Peterson, 2014). Similar to design philosophy of the two reactors described above, all the RC system components remain within the containment and TES layout will be outside the reactor building.…”

On the Sustainability and Progress of Energy Neutral Mineral Processing

“…However, the project did not result in actually building and operating an HTGR. In the case of energy neutral mineral processing, though it may be realized, HTGRs could be the first choice over other emerging HTR technology [131][132][133], such as the compact high temperature reactor (CHTR) [134,135], fluoride salt-cooled, high-temperature reactor (FHR) [136][137][138][139], gas-cooled fast reactor (GFR) [140][141][142], lead-cooled fast reactor (LFR) [143][144][145], molten salt reactor (MSR) [146] and others that may deliver process heat at temperatures higher than or equal to 600 °C. Five countries: Great Britain, the U.S., Germany, Japan and China have experience with operating and thus licensing HTGRs.…”

Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors

“…Few experiments can be adopted to validate the modified Relap5 Mod3 in simulating the transient responses of FHRs or the fluoride salt systems. The Mark1 pebble bed fluoride‐salts‐cooled high‐temperature reactor (MK1 PB‐FHR) preconceptual design has been preliminarily finished in the University of California, Berkeley . The MK1 PB‐FHR is aimed at providing a detailed design for passive residual heat removal system and increasing the inherent safety characteristics of FHRs.…”

“…The Mark1 pebble bed fluoride-salts-cooled high-temperature reactor (MK1 PB-FHR) preconceptual design has been preliminarily finished in the University of California, Berkeley. 47 The MK1 PB-FHR is aimed at providing a detailed design for passive residual heat removal system and increasing the inherent safety characteristics of FHRs. Zweibaum et al 6 built a thermal-hydraulic model of MK1 PB-FHR and performed a transient analysis on the protected loss of forced cooling (PLOFC) accident using the INL-developed Relap5-3D.…”