Review of cladding-coolant interactions during LWR accident transients

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5493782

Hobson, D O

Some of the coolant-cladding interactions that can take place during the design basis loss-of-coolant accident and the Three Mile Island loss-of-coolant accident are analyzed. The physical manifestations of the interactions are quite similar, but the time sequences involved can cause very different end results. These results are described and a listing is given of the main research programs that are involved in coolant-cladding interaction research.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5493782
• Report Number(s): CONF-800403-14; TRN: 80-008566
• Resource Relation: Conference: ANS thermal reactor safety meeting, Knoxville, TN, USA, 8 Apr 1980; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CANS
LOSS OF COOLANT
EMBRITTLEMENT
THERMAL STRESSES
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
CREEP
OXIDATION
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ZIRCALOY
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICAL PROPERTIES
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled