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Huntsville, AL|Huntsville Marriott and the Space & Rocket Center
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Tenn. legislature funds monument for Oak Ridge civil rights pioneers
In a historic photo, students gather at the Oak Ridge high school in Tennessee. (Photo: DOE)
The Tennessee legislature has approved a $3.2 million proposal to fund a monument that will honor a group of 85 black former students known as the Scarboro–Oak Ridge 85 who, with support from the Atomic Energy Commission, became the first students to enter a previously white-only public school in the southeastern United States.
"We want to make sure that Oak Ridge and the Scarboro 85 get their rightful place in the civil rights history timeline; we do not want to be left out," said John Spratling, chair of the Scarboro 85 Monument Committee.
ANS recognition: The American Nuclear Society officially recognized and honored the Scarboro 85 in 2021 by awarding the group with the inaugural Social Responsibility in the Nuclear Community Award at that year’s Annual Winter Meeting.
R. A. Lorenz, D. O. Hobson, G. W. Parker
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 502-520
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30847
Articles are hosted by Taylor and Francis Online.
Two experiments were performed in the TREAT reactor using seven-rod bundles of 27-in.-long pressurized Zircaloy-clad UO2 fuel rods to determine fuel rod failure characteristics under water reactor loss-of-coolant accident (LOCA) conditions. Fissioning in the UO2 pellets provided the most realistic duplication available of heat transfer from stored energy and decay heat expected in a reactor LOCA. The center rod of each experiment was previously irradiated in the ETR and cladding temperatures of 1800 and 2400°F were reached in a flowing steam atmosphere in the two TREAT experiments. Maximum cladding expansion averaged 36 and 60% in the two experiments with ruptures occurring over a 2¼-in. axial length. The rate of volume expansion from clad swelling was calculated and the onset of rapid expansion correlated well with the ultimate stress. Average coolant channel blockage at the worst axial location was 48% in the first experiment and 91% in the second experiment. Fission product release was <0.5%, and the release of some fission products was inhibited by the smaller rupture opening in the second experiment.
