Gas-Cooled Fast Breeder Reactor. Quarterly progress report, August 1, 1974--October 31, 1974

Technical Report · Thu Dec 12 00:00:00 EST 1974

DOI:https://doi.org/10.2172/4157100· OSTI ID:4157100

The tasks of the Gas-Cooled Fast Breeder Reactor (GCFR) program include: development of GCFR fuel, blanket, and control elements; fuels and materials development; nuclear analysis and reactor physics for GCFR core design; development of the pressure-equalization system for fuel; structural-thermal-flow tests of core assemblies; an in-pile loop facility test program plan; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and core support structure, to evaluate and develop the reactor control-rod, shutdown-rod, and core components locking mechanisms, and to evaluate the capability of PCRV internal structures to serve as postaccident fuel containment; to evaluate the pressure-boundary integrity of the prestressed concrete reactor vessel (PCRV); reactor safety; refueling-system development; component development engineering, in particular, the steam generator, helium circulator, and PCRV; shielding requirements of the GCFR; and fuel-rod engineering to evaluate the steady-state and transient performance of the GCFR fuel and blanket rods. (auth)

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: AT(04-3)-167
• NSA Number: NSA-33-002324
• OSTI ID: 4157100
• Report Number(s): GA-A-13238
• Resource Relation: Other Information: Orig. Receipt Date: 30-JUN-76
• Country of Publication: United States
• Language: English

Related Subjects

N77500* -Reactors-Power Reactors
Breeding
210500* -Nuclear Power Plants-Power Reactors
Breeding
*FUEL ELEMENTS- DESIGN
*GCFR REACTOR- SHIELDING
*REACTOR CORES
*SHIELDS
BREEDING BLANKETS
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR FUELING
REACTOR SAFETY
RESEARCH PROGRAMS
STEAM GENERATORS
SUPPORTS
TESTING
VENTS