High-Temperature Gas-cooled Reactor steam-cycle/cogeneration lead plant auxiliary heat removal: system design description
Technical Report
·
OSTI ID:5493511
The Auxiliary Heat Removal System (AHRS) is an engineered safety system included in the 2240 MW(t) HTGR-SC/C Plant to remove heat from the reactor core and primary coolant whenever heat removal through the main primary coolant loops and steam system is not available and the reactor has been tripped. As its name implies, this system functions as a backup system for the removal of heat from the reactor and thereby maintain plant protection and control of radionuclide release from the core. As designed AHRS consists of three functionally identical heat transport loops. The scope of the system includes the Auxiliary Circulator Subsystem (ACS) and the Auxiliary Heat Exchanger (AHE), both of which interface with the primary, coolant, the Auxiliary Heat Removal Control Subsystem, controlling power to the Auxiliary Circulator, and Auxiliary Cooling Water Subsystem comprising the secondary circuit that transports the heat removed from the AHE to the system ultimate heat sink for the AHRS, which is ambient air, and the Auxiliary Circulator Motor Cooling Subsystem.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76SF70046
- OSTI ID:
- 5493511
- Report Number(s):
- DOE/SF/70046-T5; HCD-32800; ON: DE84002163
- Country of Publication:
- United States
- Language:
- English
Similar Records
Primary loop heat exchanger for HTGR plant residual heat removal and auxiliary cooling system
High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant heat transport system design description
HTGR nuclear heat source component design and experience
Conference
·
Tue Mar 31 23:00:00 EST 1981
·
OSTI ID:6134108
High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant heat transport system design description
Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5583556
HTGR nuclear heat source component design and experience
Conference
·
Sat May 01 00:00:00 EDT 1982
·
OSTI ID:5061063
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
COOLING SYSTEMS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
PROCESS HEAT REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RHR SYSTEMS
SPECIFICATIONS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
COOLING SYSTEMS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
PROCESS HEAT REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RHR SYSTEMS
SPECIFICATIONS