PBF LOCA test LOC-6 fuel-behavior report. [PWR]

Technical Report · Fri Apr 01 00:00:00 EST 1983

OSTI ID:6137957

Broughton, T M; Vinjamuri, K; Hagrman, D L; Golden, D W; MacDonald, P E

This report presents the results of Loss-of-Coolant (LOC) Test LOC-6, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., for the US Nuclear Regulatory Commission. Postirradiation examination results are included, together with the results of thermal-hydraulic and fuel behavior calculations using the RELAP4 and FRAP-T6/BALON-2 computer codes. Two of the four light water reactor type fuel rods ballooned and ruptured during the test. Peak cladding temperatures at the rupture locations were high in the alpha phase (1066 and 1098/sup 0/K). The effects of initial rod internal prepressurization and prior irradiation were investigated during the experiment. The effect of rod prepressurization was found to be significant, and, for burnups of about 17,000 MWd/t, prior irradiation increased cladding circumferential strains at failure.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6137957
• Report Number(s): NUREG/CR-3184; EGG-2244; ON: DE83012115
• Resource Relation: Other Information: Includes 9 sheets of 48 and 24x reduction microfiche
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
FUEL RODS
PRESSURE GRADIENTS
REACTOR SAFETY
STRAINS
TEMPERATURE GRADIENTS
TEST FACILITIES
THERMAL STRESSES
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled