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Fuel Temperature Coefficients of Reactivity for Heavy-Water-Moderated,Cluster-Type Fuel Lattices
Abstract:Temperature coefficients of reactivity have been measured up to 600°C on cluster-type UO2 fuel for three kinds of 235U enrichment and on a hollow cluster of sus-cladding tubes by using a hot He gas loop in a heavy-water-moderated, pressure-tube-type critical assembly. A new experimental method has been developed which accurately eliminates the reactivity disturbance caused by heat leakage in the measurement of an extremely small change in reactivity. The fuel (fuel pellet, cladding land pressure-tube) temperature coefficients of reactivity obtained for the temperature range below 300°C are +1.00±0.04, ?3.48±0.13 and - 6.36±0.25 in the unit of l0-5% Δk/k.°C for 0.2%, 0.7% and 1.5%235U enrichment, respectively. In the higher temperature region above 300°C, each coefficient shifts to positive side by about 2x10-5 Δk/k.°C. Temperature coefficient of reactivity for the hollow cluster of sus-cladding tubes (cladding and pressure-tube) has a large constant value with positive sign, + (6.42±0.26) x 10-5 Δk/k.°C, all through the temperature range. A calculational model to analyze a hot-loop-type measurement of temperature coefficients with use of WIMS-D code was proposed and could be successfully applied to the present measurement.
Keywords:fuel temperature coefficient  cluster-type fuel  uranium dioxide  ATR  stainless steel cladding  hot loop  heat leakage  heterogeneity  cell design code  multi-cell  uranium 238  resonance capture  Doppler effect  helium  reactivity  temperature dependence
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