Thermal hydraulics of accelerator breeder systems for regeneration of reactor fuel assemblies

Conference · Mon Jan 01 04:00:00 EST 1979

OSTI ID:6164639

Yu, W S; Powell, J R

The following conclusions are obtained with regard to the thermal-hydraulic behavior of the Linear Accelerator Fuel Regenerator for PWR and CANDU fuel: (1) two-phase flow is a feasible coolant option for fuel element heat fluxes up to 1 x PWR (or CANDU) average value, which is the maximum design value for a LAFR; (2) two-phase flow pressure drops are low (typically 10 to 30 psi) and film temperature drops very low (typically approx. 10/sup 0/F) for PWR fuel, with inlet velocity range (50 to 75 ft/sec). A somewhat higher inlet velocity range (75 to 100 ft/sec) and pressure drop (50 to 100 psi) is necessary for CANDU fuel, however, to prevent dry out.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6164639
• Report Number(s): BNL-25880; CONF-790423-6
• Country of Publication: United States
• Language: English

Related Subjects

43 PARTICLE ACCELERATORS
430303* -- Particle Accelerators-- Experimental Facilities & Equipment
ACCELERATOR BREEDERS
BEAMS
COOLING SYSTEMS
ENERGY RANGE
FLUID FLOW
FUEL ASSEMBLIES
GEV RANGE
GEV RANGE 01-10
HYDROGEN COMPOUNDS
NEUTRON FLUX
NUCLEON BEAMS
OXYGEN COMPOUNDS
PARTICLE BEAMS
PROTON BEAMS
RADIATION FLUX
STEAM
TARGETS
WATER