Natural convection boiling of sodium in a simulated FBR fuel assembly subchannel

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

OSTI ID:5902714

Garrison, P W; Morris, R H; Montgomery, B H

A series of single channel sodium boiling experiments were conducted in the Sodium Boiling Test (SBT) Facility at the Oak Ridge National Laboratory. The objective of these tests was to determine the maximum power that can be transferred to the coolant in a fuel assembly subchannel when the flow is driven by natural convection. Stable boiling was achieved for test times approaching one hour in duration for powers below the critical level. The power corresponding to dryout in these tests compares well with predictions from an earlier water simulation of fuel assembly voiding behavior.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: Not Available; USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5902714
• Report Number(s): CONF-790816-20
• Country of Publication: United States
• Language: English

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ACCIDENTS
AFTER-HEAT
AFTER-HEAT REMOVAL
BOILING
BREEDER REACTORS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NATURAL CONVECTION
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
REMOVAL
TEST FACILITIES