Irradiation Effects Test Series: Test IE-2. Test results report. [PWR]

Technical Report · Mon Aug 01 04:00:00 EDT 1977

DOI:https://doi.org/10.2172/7211090· OSTI ID:7211090

Allison, C. M.; Croucher, D. W.; Ploger, S. A.; Mehner, A. S.

The report describes the results of a test using four 0.97-m long PWR-type fuel rods with differences in diametral gap and cladding irradiation. The objective of this test was to provide information about the effects of these differences on fuel rod behavior during quasi-equilibrium and film boiling operation. The fuel rods were subjected to a series of preconditioning power cycles of less than 30 kW/m. Rod powers were then increased to 68 kW/m at a coolant mass flux of 4900 kg/s-m/sup 2/. After one hour at 68 kW/m, a power-cooling-mismatch sequence was initiated by a flow reduction at constant power. At a flow of 2550 kg/s-m/sup 2/, the onset of film boiling occurred on one rod, Rod IE-011. An additional flow reduction to 2245 kg/s-m/sup 2/ caused the onset of film boiling on the remaining three rods. Data are presented on the behavior of fuel rods during quasiequilibrium and during film boiling operation. The effects of initial gap size, cladding irradiation, rod power cycling, a rapid power increase, and sustained film boiling are discussed. These discussions are based on measured test data, preliminary postirradiation examination results, and comparisons of results with FRAP-T3 computer model calculations.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• Sponsoring Organization: US Energy Research and Development Administration (ERDA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 7211090
• Report Number(s): TREE-NUREG-1074
• Country of Publication: United States
• Language: English

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ACCIDENTS
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FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
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PHYSICAL PROPERTIES
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REACTOR COMPONENTS
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SIMULATION
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS