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U.S. Department of Energy
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Fission gas release in LWR fuel measured during nuclear operation

Conference ·
OSTI ID:5553784
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Halden, Norway, to measure the release of Xe, Kr, and I fission products from typical light water reactor design fuel pellets. Helium gas is used to sweep the Xe and Kr fission gases out of two of the Instrumented Fuel Assembly 430 fuel rods and to a gamma spectrometer. The measurements of Xe and Kr are made during nuclear operation at steady state power, and for /sup 135/I following reactor scram. The first experiments were conducted at a burnup of 3000 MWd/t UO/sub 2/, at bulk average fuel temperatures of approx. 850 K and approx. 23 kW/m rod power. The measured release-to-birth ratios (R/B) of Xe and Kr are of the same magnitude as those observed in small UO/sub 2/ specimen experiments, when normalized to the estimated fuel surface-to-volume ratio. Preliminary analysis indicates that the release-to-birth ratios can be calculated, using diffusion coefficients determined from small specimen data, to within a factor of approx. 2 for the IFA-430 fuel. The release rate of /sup 135/I is shown to be approximately equal to that of /sup 135/Xe.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
5553784
Report Number(s):
CONF-800403--32
Country of Publication:
United States
Language:
English