Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]
Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-basis accident sequences to assess LWR core coolability for licensing purposes. Results of a recent 8 X 8 test indicate that models derived from smaller test arrays may not be representative of the behavior in large arrays, particularly for those temperature ranges in which large deformation can be expected. Two MRBT LOCA simulation tests conducted under the same nominal conditions (approx. 10 K/s heating rate from approx. 340/sup 0/C to failure at approx. 770/sup 0/C) were examined to determine the effects of array size and boundary conditions on deformation.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5275056
- Report Number(s):
- CONF-820609-39; ON: DE82017420; TRN: 82-015960
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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Preliminary Multirod Burst Test Program results and implications of interest to reactor safety evaluations
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CANS
LOSS OF COOLANT
DEFORMATION
FAILURES
THERMAL STRESSES
PWR TYPE REACTORS
FUEL ASSEMBLIES
REACTOR SAFETY
TEST FACILITIES
ZIRCALOY 4
ACCIDENTS
ALLOYS
REACTOR ACCIDENTS
REACTORS
SAFETY
STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
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