Forced-convection boiling tests performed in parallel simulated LMR fuel assemblies

Conference · Sun Apr 21 00:00:00 EST 1985

OSTI ID:5574659

Rose, S D; Carbajo, J J; Levin, A E; Lloyd, D B; Montgomery, B H; Wantland, J L

Forced-convection tests have been carried out using parallel simulated Liquid Metal Reactor fuel assemblies in an engineering-scale sodium loop, the Thermal-Hydraulic Out-of-Reactor Safety facility. The tests, performed under single- and two-phase conditions, have shown that for low forced-convection flow there is significant flow augmentation by thermal convection, an important phenomenon under degraded shutdown heat removal conditions in an LMR. The power and flows required for boiling and dryout to occur are much higher than decay heat levels. The experimental evidence supports analytical results that heat removal from an LMR is possible with a degraded shutdown heat removal system.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5574659
• Report Number(s): CONF-850410-40; ON: TI85011429
• Resource Relation: Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985; Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ASSEMBLIES
AFTER-HEAT REMOVAL
LMFBR TYPE REACTORS
BOILING
DRYOUT
FORCED CONVECTION
REACTOR SHUTDOWN
RHR SYSTEMS
SIMULATION
BREEDER REACTORS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
MASS TRANSFER
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SHUTDOWNS
210500* - Power Reactors
Breeding