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Accession Number DE2012-1054142
Title Advanced High-Temperature Reactor Dynamic System Model Development. April 2012 Status.
Publication Date Apr 2012
Media Count 61p
Personal Author A. L. Qualls M. S. Cetiner T. L. Wilson
Abstract The Advanced High-Temperature Reactor (AHTR) is a large-output fluoride-salt-cooled hightemperature reactor (FHR). An early-phase preconceptual design of a 1500 MW(e) power plant was developed in 2011. An updated version of this plant is shown. FHR's feature lowpressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTR is designed to be a walk away reactor that requires no action to prevent large off-site releases following even severe reactor accidents. This report describes the development of dynamic system models used to further the AHTR design toward that goal. These models predict system response during warmup, startup, normal operation, and limited off-normal operating conditions. Severe accidents that include a loss-of-fluid inventory are not currently modeled. The scope of the models is limited to the plant power system, including the reactor, the primary and intermediate heat transport systems, the power conversion system, and safety-related or auxiliary heat removal systems. The primary coolant system, the intermediate heat transport system and the reactor building structure surrounding them are shown. These systems are modeled in the most detail because the passive interaction of the primary system with the surrounding structure and heat removal systems, and ultimately the environment, protects the reactor fuel and the vessel from damage during severe reactor transients. The reactor silo also plays an important role during system warmup.
Keywords Advanced High-Temperature Reactor(AHTR)
Cooling systems
Fluorides
Fuel cycle
Nuclear fuels
Nuclear power plants
Nuclear reactors
Reactor cores
Reactor vessels


 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77H - Reactor Engineering & Nuclear Power Plants
77I - Reactor Fuels & Fuel Processing
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1308
Contract Number DE-AC05-00OR22725

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