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The deadline arrives: Checking in on the Reactor Pilot Program
On May 23, 2025, President Trump signed Executive Order 14301, “Reforming Nuclear Reactor Testing at the DOE,” which instructed the Department of Energy to create a Reactor Pilot Program (RPP)—a new system in which companies could pursue DOE authorization to build and test their first-of-a-kind nuclear technologies. EO 14301 set an ambitious goal for that program: three reactors achieving criticality by July 4, 2026.
Seungwon Shin, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 24-39
Technical Paper | doi.org/10.13182/NSE07-A2682
Articles are hosted by Taylor and Francis Online.
The behavior of an evaporating thin liquid film on a nonuniformly heated cylindrical rod with both parallel and cross vapor flow has been numerically investigated. The aim is to develop a mechanistic model for local dryout in boiling water reactors (BWRs). The liquid film on a full-length BWR fuel rod may experience significant axial and azimuthal heat flux gradients and cross flow due to variations in the thermal-hydraulic conditions in surrounding subchannels caused by proximity to an inserted control blade tip and/or the top of part-length fuel rods. Such heat flux gradients coupled with localized cross flow may cause the liquid film on the fuel rod surface to rupture by hydrodynamic instability, thereby forming a dry hot spot. These localized dryout phenomena cannot be accurately predicted by traditional subchannel analysis methods in conjunction with empirical dryout correlations. To this end, a numerical model based on the level contour reconstruction method has been developed. The model includes a ghost-cell extrapolation technique to handle the complex interface geometry. Additionally, a sharp interface temperature technique has been implemented. Application of the model to BWR fuel rods shows that localized cross flow coupled with heat flux gradients can lead to liquid film rupture and dry spot formation.