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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.
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A high-fidelity safety analysis method for pressurized water reactors (PWRs) is presented using a multiscale and multiphysics coupled code. Computational resolution of the conventional safety analysis can be greatly improved using this method in which the whole reactor vessel is modeled at a subchannel scale with around 5 million calculation meshes. Three-dimensional thermal hydraulics inside the reactor vessel is simulated using CUPID-RV with subchannel-scale thermal-hydraulic models for the reactor core. The subchannel models were validated using the legacy rod bundle experiments including single- and two-phase flow tests that were used in the validation of other subchannel analysis codes. The three-dimensional mesh was generated for the reactor vessel. Structured meshes were used in the core region for the subchannel model, and body-fitted unstructured meshes were applied for the downcomer, lower and upper plenums, and hot and cold legs. The number of meshes was optimized for a practical calculation. A three-dimensional core kinetics code (MASTER) and a one-dimensional system analysis code (MARS) were coupled with CUPID-RV for an accident analysis of PWRs. Subchannel-scale full-core steam line break accident analysis of the OPR1000 PWR was realized using the coupled code (MASTER/CUPID-RV/MARS) with a reasonable computation time, and thus, the present method can be used as a practical tool for three-dimensional safety analysis of PWRs.