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OSTP memo guides space nuclear plan
A White House Office of Science and Technology Policy (OSTP) memorandum released on Tuesday guides NASA, the Department of Energy, and the Department of Defense on their roles in deploying near-term space nuclear power.
This follows a series of NASA announcements last month—driven by the executive order “Ensuring American Space Superiority,” issued by Trump in December—including an ambitious timeline for establishing a moon base, which would rely on fission surface power (FSP) to survive the long lunar night at the moon’s south pole, and plans for a nuclear electric propulsion (NEP) rocket to be launched in 2028.
K. Podila, Q. Chen, P. Pfeiffer, X. Huang, S. Golesorkhi, A. Trottier, A. John, S. Kelly
Nuclear Science and Engineering | Volume 199 | Number 12 | December 2025 | Pages 2172-2192
Regular Research Article | doi.org/10.1080/00295639.2025.2475621
Articles are hosted by Taylor and Francis Online.
Pursuant to Canada’s small modular reactor (SMR) action plan to achieve net-zero emissions, a SMR based on gas-cooled reactors (GCRs) is one of the potential concepts among the non-water-cooled reactor technologies to be considered for deployment in the near future in Canada. A coupled modeling approach to account for feedback effects using higher-fidelity solutions is becoming increasingly viable due to improvements in phenomenological models and advanced computing. This study aims to improve simulation accuracy for the prismatic block GCR scenarios of interest using an integrated coupled modeling toolset that loosely couples computational fluid dynamics (CFD), system thermalhydraulics (TH), and neutronics codes.
The differentiating aspect of this study is the execution of three-way coupled analyses for the GCRs that can account for both the component- and system-level scales. Within this study, a part of the reactor core was simulated using CFD, coupled with a one-dimensional system TH code for the solution of the rest of the reactor circuit. The power feedback effects inside the reactor core simulated with CFD were obtained from a neutronics solver. An explicit representation of the core components was undertaken in the CFD model to facilitate the detailed modeling of the coolant flow within the channels and its interaction with the reflectors, fuel, and control rods.
Two industrially relevant test operating scenarios, fully withdrawn and incremental increase of insertion level of control rods, were simulated to showcase the suitability of the coupled analyses. The reactivity coefficients and control rod worth using the coupled multiphysics analyses are presented. The results demonstrate the capability of the developed algorithm for coupling three modeling disciplines for its application in GCR core simulations.