FY21 RadNeuro Annual Review Presentation
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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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In the second year, the IRIS team developed the components necessary for successful offline deployment of the IRIS services. This includes custom automated speech recognition training on NASA audio data, and in-house development and integration of online and offline conversational services. Lastly, the team worked on integrating the IRIS technology with stakeholders and projects that have a strong need for voice interaction.
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An in-depth study of plasma activated water (PAW) generation was conducted to link changes in power supply, electrode material, input gas, and treatment time to the resulting reaction chemistry. These changes in chemistry can help tailor PAW for different space applications. An AC, DC, and nanosecond (ns) pulsed power supply were each used to generate PAW with stainless steel, copper, tungsten, or platinum (Pt) electrodes while utilizing air, nitrogen (N2), carbon dioxide (CO2), helium (He), or argon (Ar) as the feed gas. Tap or deionized (DI) water was treated for 1 to 15 minutes, and the generated PAW was tested for changes in pH, conductivity, oxidation reduction potential, nitrates (NO3-), ammonium (NH4+), and peroxide. Calculations showed that the production of reactive nitrogen species was the leading cause of pH and conductivity changes. The DC generated air plasma was able to reduce the pH of DI water and generate NO3‑. The pulsed supply, operating at 20% of the input power of the DC supply, lowered the pH generated NO3‑. When a simulated Martian gas mixture of 95% CO2 and 5% N2 was used as the feed gas, NO3‑ was generated with the DC and pulsed supplies, respectively. Mixing PAW with plasma generated ash from inedible biomass allowed pH control, thus enhancing PAW’s potential use for sanitation applications. The large shift in pH was used to study sanitation effects of Escherichia coli (E. coli) reduction and Staphylococcus aureus (S. aureus), in which log reductions were found to be negligible. Additionally, the plasma generated ash in combination with PAW was also implemented in 10-day microgreen growth trials, in which PAW and ash resulted in quicker emergence of the microgreens compared to the standard growth conditions and comparable dry masses to Hoagland’s nutrient solution treated samples.
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Webinar presentation on NREL's high-performance computing (HPC) allocation process for Fiscal Year 2021.
This is a PDF file that contains information related to ATR operating cycle dates, lobe powers, and core positions. This is an integrated strategic operations schedule for ATR core insertions and accompanying cycles.
This report provides an end-of-year summary that reflects the progress and status of Idaho National Laboratory’s activities concerning advanced reactor regulatory framework development and implementation in the U.S. This work was done in FY 2021 and supported regulatory development for the U.S. Department of Energy (DOE) Advanced Reactor Technologies Program. These activities are managed by Idaho National Laboratory on behalf of the U.S. DOE.
This report will focus on progress and development in establishment of refabrication/instrumentation capability at Idaho National Laboratory (INL). Refabrication/instrumentation is considered an enabling capability that allows access to fuel materials at any point in their life cycle. It is also critical in supporting deployment and qualification of ATF materials as many candidate materials are already undergoing irradiation as lead test rods (LTR) in commercial nuclear power plans (NPP) and irradiation in ATR alone can not produce the quantities of materials necessary to support qualification.
This report provides the status of creep, fatigue, and creep-fatigue testing that transpired in Fiscal Year 2021 at Argonne National Laboratory, Idaho National Laboratory and Oak Ridge National Laboratory. This testing is being conducted to develop the data package to qualify Alloy 709 in Section III, Division 5 of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code. This would permit the use of Alloy 709 for elevated-temperature nuclear construction. Preliminary results continue to demonstrate the improved creep and fatigue resistance of Alloy 709 compared to 316H stainless steel.
This report summarizes the progress made on reducing the joining time for thick plates of Alloy 740H. Modeling of deep penetration laser welding of Alloy 740H continues with the goal of explaining cracking in the weld that is observed in experimental laser welds in this alloy. Experimental work was also performed to understand factors influencing hybrid laser arc weld quality as a function of the arc and laser parameters. Laser welds and hybrid laser arc welds have been made using best practices up this point in the project. Welded materials have been sent to a commercial vendor to make creep specimens and perform short term creep tests to help evaluate the quality of the welds that have been made so far.
Abstract not provided.