INTERIM REFERENCE DESIGN GAS-COOLED, HEAVY-WATER-MODERATED PRESSURE-TUBE REACTOR PROTOTYPE (GCPTR)

Technical Report · Mon Sep 01 04:00:00 EDT 1958

OSTI ID:4807222

The design concepts of the gas-cooled, heavy-watermoderated, pressure- tube reactor are presented and discussed. The reactor power is 175 Mw thermal and 58 Mw electric, giving a net thermal efficiency of 33.2%. The prototype is designed so that it may be adaptable to a 200 Mw electric output plant that will use natural uranium as a fuel. The first fuel load of the prototype will use slightly-enriched uranium dioxide with stainless steel cladding. High thermal performance (heat rate of 10,300 Btu/kwh) is achieved by operating at a gas outlet temperature of at least 1000 deg F. Good neutron economy results from the use of heavy water as the moderator and the use of core and fuel materials of low neutron cross section. A single-pressure cycle uses a feedwater temperature of 256 deg F and produces steam at 1800 psi/1000 deg F with reheat to 1000 deg F. (N.W.R.)

• Research Organization: General Nuclear Engineering Corp., Dunedin, Fla.
• NSA Number: NSA-16-026594
• OSTI ID: 4807222
• Report Number(s): GNEC-74
• Country of Publication: United States
• Language: English

Related Subjects

CROSS SECTIONS
EFFICIENCY
FUEL CANS
GAS COOLANT
GCPR
HEAVY WATER MODERATOR
HIGH TEMPERATURE
NATURAL URANIUM FUEL
OPERATION
PERFORMANCE
PLANNING
POWER
POWER PLANTS
PRESSURE
REACTOR TECHNOLOGY
REACTORS
STAINLESS STEELS
STEAM
THERMODYNAMICS
TUBES
URANIUM DIOXIDE