Reactivity initiated accident test series Test RIA 1-4 fuel behavior report. [PWR; BWR]

Technical Report · Sat Sep 01 04:00:00 EDT 1984

OSTI ID:6338876

Cook, B A; Martinson, Z R

This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reactor hot-startup system conditions. The test resulted in estimated axial peak, radial average fuel enthalpies of 234 cal/g UO/sub 2/ on the center rod, 255 cal/g UO/sub 2/ on the side rods, and 277 cal/g UO/sub 2/ on the corner rods. Test RIA 1-4 was conducted to investigate fuel coolability and channel blockage within a bundle of preirradiated rods near the present enthalpy limit of 280 cal/g UO/sub 2/ established by the US Nuclear Regulatory Commission. The test design and conduct are described, and the bundle and individual rod thermal and mechanical responses are evaluated. Conclusions from this final test and the entire PBF RIA Test Series are presented.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6338876
• Report Number(s): NUREG/CR-3938; EGG-2336; ON: TI85001844
• Country of Publication: United States
• Language: English

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