High-Temperature Gas-cooled Reactor steam-cycle/cogeneration lead plant reactor vessel: system design description
The Reactor Vessel System contains the primary coolant inventory within a gas-tight pressure boundary, and provides the necessary flow paths and overpressure protection for this pressure boundary. The Reactor Vessel System also houses the components of the Reactor System, the Heat Transport System, and the Auxiliary Heat Removal System. The scope of the Reactor Vessel System includes the prestressed concrete reactor vessel (PCRV) structure with its reinforcing steel and prestressing components; liners, penetrations, closures, and cooling water tubes attached to the concrete side of the liner; the thermal barrier (insulation) on the primary coolant side of the liner; instrumentation for structural monitoring; and a pressure relief system. Specifications are presented.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76SF70046
- OSTI ID:
- 5564950
- Report Number(s):
- DOE/SF/70046-T6; HCD-31100; ON: DE84002646
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant reactor system design description
Gas-cooled nuclear reactor
Related Subjects
HTGR TYPE REACTORS
REACTOR VESSELS
PROCESS HEAT REACTORS
SPECIFICATIONS
PRESTRESSED CONCRETE
BUILDING MATERIALS
CONCRETES
CONTAINERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS
REACTORS
210900* - Nuclear Power Plants- Process Heat Reactors- (-1987)
210300 - Power Reactors
Nonbreeding
Graphite Moderated