Irradiation effects test series test IE-1 test results report. [PWR]

Technical Report · Tue Mar 01 04:00:00 EST 1977

DOI:https://doi.org/10.2172/7216063· OSTI ID:7216063

Quapp, W. J.; Allison, C. M.; Farrar, L. C.; Mehner, A. S.

The report describes the results of the first programmatic test in the Nuclear Regulatory Commission Irradiation Effects Test Series. This test (IE-1) used four 0.97m long PWR-type fuel rods fabricated from previously irradiated Saxton fuel. The objectives of this test were to evaluate the effect of fuel pellet density on pellet-cladding interaction during a power ramp and to evaluate the influence of the irradiated state of the fuel and cladding on rod behavior during film boiling operation. Data are presented on the behavior of irradiated fuel rods during steady-state operation, a power ramp, and film boiling operation. The effects of as-fabricated gap size, as-fabricated fuel density, rod power, and power ramp rate on pellet-cladding interaction are discussed. Test data are compared with FRAP-T2 computer model predictions, and comments on the consequences of sustained film boiling operation on irradiated fuel rod behavior are provided.

• Research Organization: SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
• Sponsoring Organization: US Energy Research and Development Administration (ERDA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 7216063
• Report Number(s): TREE-NUREG-1046
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILING
FILM BOILING
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS