High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant heat transport system design description

Technical Report · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5583556

The Heat Transport System consists of the pressurized helium primary coolant volume enclosed within the prestressed concrete reactor vessel liner and of the components associated with the transfer of heat emerging from the core to the feedwater in the steam generators. Specifically, the Heat Transport System helium is that contained within the four main and the three auxiliary loops (including the ducts), the plenum above the core, the core itself and the plenum below the core. This helium interfaces with the prestressed concrete reactor vessel liner and its closures, the core, the thermal barriers and the portions of the Heat Transport and Auxiliary Heat Removal Systems components which form the primary coolant pressure retaining boundaries. Specifications are presented.

• Research Organization: GA Technologies, Inc., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 5583556
• Report Number(s): DOE/SF/70046-T4; HCD-32100; ON: DE84002808
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
SPECIFICATIONS
PROCESS HEAT REACTORS
BLOWERS
STEAM GENERATORS
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
VAPOR GENERATORS
210900* - Nuclear Power Plants- Process Heat Reactors- (-1987)
210300 - Power Reactors
Nonbreeding
Graphite Moderated