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Critical heat flux experiments in an internally heated annulus with a non-uniform, alternate high and low axial heat flux distribution

Description: Critical heat flux experiments were performed with an alternate high and low heat flux profile in an internally heated annulus. The heated length was 84 inches (213 cm) with a chopped wave heat flux profile over the last 24 inches (61 cm) having a maximum-to-average heat flux ratio of 1.26. Three test sections were employed: one with an axially uniform heat flux profile as a base case and two with 60 inch (152 cm) uniform and 24 inch (61 cm) alternating high and low heat flux sections. The thir… more
Date: February 1981
Creator: Beus, S. G. & Seebold, O. P.
Partner: UNT Libraries Government Documents Department
open access

Fission gas release from oxide fuels at high burnups

Description: The steady state gas release, swelling and densification model previously developed for oxide fuels has been modified to accommodate the slow transients in temperature, temperature gradient, fission rate and pressure that are encountered in normal reactor operation. The gas release predictions made by the model were then compared to gas release data on LMFBR-EBRII fuels obtained by Dutt and Baker and reported by Meyer, Beyer, and Voglewede. Good agreement between the model and the data was foun… more
Date: February 1, 1981
Creator: Dollins, C. C.
Partner: UNT Libraries Government Documents Department
open access

Swelling and gas release in oxide fuels during fast transients

Description: The previously reported swelling and gas release model for oxide fuels has been modified to predict fission gas bahavior during fast temperature transients. Under steady state or slowly varying conditions it has been assumed in the previous model that the pressure caused by the fission gas within the gas bubbles is in equilibrium with the surface tension of the bubbles. During a fast transient, however, net vacancy migration to the bubbles may be insufficient to maintain this equilibrium. In or… more
Date: February 1, 1981
Creator: Dollins, C. C.
Partner: UNT Libraries Government Documents Department
open access

Spatial distribution measurements of fission neutrons in water as an oxygen data test

Description: The spatial distribution of the total neutron density from a /sup 252/Cf source in pure water was measured to high statistical precision at distances from 11 to 80 cm from the source. Assuming the adequacy of the ENDF/B-IV hydrogen, and reasonable constraints on the fission spectrum mean energy, good agreement between experiment and a one-dimensional transport calculation was obtained for both ENDF/B-III and IV oxygen, with Version III slightly better. However, small residual differences remain… more
Date: February 1978
Creator: Green, L. & Ullo, J.J.
Partner: UNT Libraries Government Documents Department
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