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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Orion Power Transfer: Impacts of a Battery-on-Bus Power System Architecture
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High Efficiency Stirling Power Conversion Technologies for Radioisotope and Fission Nuclear Power Systems
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High Efficiency Stirling Power Conversion Technologies for Radioisotope and Fission Nuclear Power Systems
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NASA’s Interest in Radiation Tolerance and Requirements of Candidate Technologies for Fission Surface Power and Further Relevance to Dynamic Radioisotope Power Systems
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NASA Glenn Power Division Power Management and Distribution Branch (PMAD)
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Virtual Power Plant utilization to Drive Energy Efficiency & Power Market Optimization for Multifamily Buildings
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Spatial power profiling method using visual information in reactors with optically transparent coolants
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Three dimensional reactor power profile reconstruction using Cerenkov radiation
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A novel supercritical CO2 recompression Brayton power cycle for power tower concentrating solar plants
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Techno-economic analysis of a combined power plant CO2 capture and direct air capture concept for flexible power plant operation
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Strain mapping of GaN substrates and epitaxial layers used for power electronic devices by synchrotr
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Protein Footprinting: Auxiliary Engine to Power the Structural Biology Revolution
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Wind-Power Generator Technology Research Aims to Meet Global-Wind Power Ambitions
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Experimental investigation of steady state power balance in double null and single null H mode plasmas in MAST Upgrade
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Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E x B drift flows
Edge-plasma simulations of a baffled, long-legged divertor in DIII-D, performed using the multi-fluid code UEDGE, indicate that the position of the detachment front is constrained to the location of the pump duct along the low-field side (LFS) baffle. Simulations including magnetic and E x B drifts were performed for 12.5 MW deuterium plasmas including intrinsic carbon and seeded neon to assess the optimal location of the LFS divertor pump to create a stable detachment front between the target and the X-point. The radiation front position in the simulations, taken to be indicative of the detachment front, can be controlled between the pump and X-point in the favorable magnetic field direction for H-mode access by moving the pump duct location upstream of the target along the LFS baffle. In the unfavorable magnetic field direction, the radial E θ x B drift flows are directed towards the pumping surface, efficiently removing the injected deuterium gas and limiting the sensitivity of the radiation front location to the gas injection rate. The role of pumping rate and drift direction on the pumping efficiency are also found to affect the divertor plasma conditions and detachment front location in UEDGE simulations.