Progress Towards the Scalable Production of Perovskite Solar Cells Using a High Throughput Roll-to-Roll Platform
Progress Towards the Scalable Production of Perovskite Solar Cells Using a High Throughput Roll-to-Roll Platform
Druffel, Thad↗
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Results for “progress”
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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Progress Report on Model Development for the Transport of Aerosol through Microchannels
This report summarizes the current progress in the development of a phenomenological model of aerosol transport, deposition, and plugging through microchannels. The purpose is to introduce a generic, reliable numerical model for the prediction of aerosol transport, deposition, and plugging in leak paths while accounting for potential plugging formation, to a user community involving researchers, regulators, and industry. In that regard, a Graphical User Interface (GUI) was generated by integrating the individual MATLAB scripts that make up the model and adding additional features to aid the general understanding of the problem to a user. This report focuses on the model development and features included. Further, predictions from the GUI are compared with experimental data for validation. The strength of the GUI is the ability of a user to plug in basic parameters such as the initial pressure conditions and canister model specifications in order to obtain a first principal approximation of vital information such as the blowdown pressure differential, aerosol penetration, and deposition as a function of time. The user can obtain this without the know-how of the underlying MATLAB scripts and thus enables the model to be readily applied by regulators, industry, and shareholders to reduce the uncertainty in the off-site radiological consequences. The report also lists future tasks under this work scope. This includes ongoing efforts to include additional crack geometries (divergent and divergent-convergent slots) to the model; GUI development and improvement based on feedback from users, and integration of aerosol source term data from Sibling Pin tests into the model as we approach realistic canister stress corrosion cracking–induced aerosol release scenarios.
54 ENVIRONMENTAL SCIENCES↗
AC Transit Fuel Cell Electric Bus Progress Report (Data Period Focus: Jan. 2020 through Dec. 2020) [Slides]
This report presents early results from a deployment of fuel cell electric buses (FCEBs) operated by Alameda Contra-Costa Transit (AC Transit) in the east bay area of California. The ten FCEBs, produced by New Flyer, feature an electric drive propulsion system powered by a Ballard fuel cell system. The project team is collaborating with the U.S. Department of Energy (DOE) and DOE's National Renewable Energy Laboratory (NREL) to evaluate the buses in revenue service. The goal of this evaluation is to compare the FCEB performance to that of conventional technology and to track progress over time toward meeting the technical targets set by DOE and the Department of Transportation (DOT). The FCEBs were delivered beginning in late-2019. The data period covers January 2020 through July 2020. NREL collects data on two different baseline bus fleets for comparison: five 2017 model year diesel buses and five 2016 model year diesel hybrid buses.
30 DIRECT ENERGY CONVERSION↗
A Progress Report for a 44-month Aging Study on Nitroplasticizer (NP) Stability – Summary of KF and TGA Results
In the past few years, a 44-month long aging experiment was conducted under various aging conditions. The properties of aged nitroplasticizer (NP) samples were analyzed using Fourier transform infrared spectroscopy, Karl Fischer (KF) titration, thermogravimetric analysis (TGA), liquid chromatography tandem quadrupole time of flight mass spectrometry, and ion chromatography. In this progress report, complete KF and TGA results are reported and discussed.
36 MATERIALS SCIENCE↗
Pages Extracted from F Division Monthly Progress Reports March 1945 to November 1945
This provides a compilation of Bretscher’s Group F-3 monthly progress reports in 1945. They are of historical importance because they cover the period when Los Alamos measured the DT cross section and discovered the large resonance enhancement, at DT energies relevant to thermonuclear application. See the July 1945 report in particular. Prior to this, the DT cross section was first measured at Purdue in 1943, but at much higher energies that are less relevant for applications. Numerical values are not given here – they can be found in the 1946 report LA-582 and Phys. Rev. 75, 1154 (1949).
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Fusion Materials Semiannual Progress Report for the Period Ending December 31, 2022
This is the seventy-third in a series of semiannual technical progress reports on fusion materials science activity supported by the Fusion Energy Sciences Program of the U.S. Department of Energy. It covers the period ending December 31, 2022. This report focuses on research addressing the effects on materials properties and performance of exposure to the neutronic, thermal and chemical environments anticipated in the chambers of fusion experiments and energy systems. This research is a major element of the national effort to establish the materials knowledge base for an economically and environmentally attractive fusion energy source. Research activities on issues related to the interaction of materials with plasmas are reported separately. The results reported are the products of a national effort involving a number of national laboratories and universities. A large fraction of this work, particularly in relation to fission reactor irradiations, is carried out collaboratively with partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of fusion materials scientists to the broader fusion community, both nationally and worldwide. This report has been compiled by Stephanie Melton, Oak Ridge National Laboratory. Her efforts, and the efforts of the many persons who made technical contributions, are gratefully acknowledged.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
A Progress Report for a 44-month Aging Study on Nitroplasticizer (NP) Stability - Summary of DFT and FTIR Results
In the past few years, a 44-month long aging experiment was conducted under various aging conditions. The properties of aged nitroplasticizer (NP) samples were analyzed using Fourier transform infrared spectroscopy, Karl Fischer (KF) titration, thermogravimetric analysis (TGA), liquid chromatography tandem quadrupole time of flight mass spectrometry (LC/QTOF), and ion chromatography (IC). In this progress report, some FTIR results are documented and discussed. On the theoretical front, density functional theory (DFT) calculations were carried out. Some DFT results are discussed as well.
36 MATERIALS SCIENCE↗
Progress on Producing an ODS Ferritic Alloy by High Deformation Processing of Reactive Powders
Oxide dispersion-strengthened (ODS) ferritic alloys, such as 14YWT, are considered as benchmarks for fuel cladding and core structural materials in advanced nuclear energy reactor systems that require high temperature strength and creep properties as well as resistance to radiation damage. Unfortunately, the popular processing method of mechanical alloying (MA) is time-consuming, incurs high manufacturing costs, and typically produces anisotropy in the microstructure and mechanical properties of ODS ferritic alloys. These considerations hinder their acceptance in many high-performance, high-temperature materials for advanced nuclear energy reactors. This work package is pursuing an alternative solid-state processing to MA involving high deformation at high temperatures for producing an ODS ferritic alloy for fuel cladding. This report summarizes the concept for this processing method and the progress toward selecting the reactive and ferritic alloy powders, preparing 316L stainless steel cans for filling with blended powder followed by degassing, and choosing the heat treatments and forging parameters for performing the first two forging experiments. The preliminary results of optical microscopy performed on polished samples that were cut in three orthogonal directions revealed remnant porosity in both samples. The analysis of the porosity using ImageJ revealed a lesser amount of ~2.49% in the HiLoMe-1 sample that was processed with the three heat treatments and forging parameters compared to ~5.70% for the Hi-1 sample that was processed with only the first sintering heat treatment and forging parameter. These initial results will provide insights that can be leveraged to improve the densification of the powders in future forging experiments that will be continued into FY24 for determining the optimum heat treatments and forging parameters coupled with detailed microstructure characterization studies for producing the ODS ferritic alloy.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Progress on Design and Production of Oxide Dispersion–Strengthened Alumina-Forming Austenitic Alloys for Nuclear Applications
Alumina-forming austenitic (AFA) alloys are a promising class of nuclear materials due to their high-temperature oxidation/corrosion resistance and mechanical properties. Unfortunately, these alloys are limited in use for core material applications, specifically in their use as nuclear fuel cladding. Improving these alloys through a fine dispersion of oxide precipitates and thus increasing the effective irradiation sink strength of the alloy system may mitigate many of the degradation phenomena expected during alloy deployment (such as high-temperature helium embrittlement for lead-cooled fast reactor applications). This work package has started using a combination of conventional and advanced manufacturing approaches to the fabrication of oxide dispersion–strengthened (ODS) AFA materials. As such, this report summarizes progress to date in the fabrication of new compositions of these ODS AFA materials with a focus on reactor-specific design and a multifaceted manufacturing approach. Two different compositions of AFA gas-atomized powders were procured, and 200 g of each have been prepared using mechanical alloying with the expectation of high-temperature consolidation in Q1 of FY24. In addition, an approach to use reactive cover gases to promote additional precipitate formation has been developed for implementation in FY24 as a direct comparison with conventionally manufactured alloys.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Improving Fission Products at CARIBU: Near Field Detection (Q4/FY23 Quarterly Progress Report)
We have addressed another round of referees’ comments and resubmitted our mass measurement of the isomer and ground state of 128 Sb to Phys. Rev. Letters. One of the referees recommended publication so we anticipate this will be the last round with the referees. This paper focuses on the astrophysical implications of our measurement, as we can directly measure the excitation energy of the isomer along with other observables like the isomer to ground state ratio produced in the fission of 252 Cf. With our summer student Asha, we were able to determine that there was an error in our Gas Counter simulations, which has been corrected and is now implemented in our 111 Ag simulations. This report describes the progress on this effort from July until August 2023. We have paused the work on this project in the last 7 Weeks while the PI was on leave. We are resuming the work on this effort in early October.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Recent progress towards incorporating radiochemical analysis in LANL ASC codes
This document summarizes the recent progress towards incorporating charged-particle radiochemical (RadChem) analysis in different LANL codes within the Advanced Scientific Computing (ASC) Program. The first section is focused on xRAGE and the implementation of the necessary physics packages to build an in-line RadChem capability. The second section provides a summary of the current RadChem postprocessing capabilities.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Fusion Materials Semiannual Progress Report for the Period Ending June 30, 2023
This is the seventy-fourth in a series of semiannual technical progress reports on fusion materials science activity supported by the Fusion Energy Sciences Program of the U.S. Department of Energy. It covers the period ending June 30, 2023. This report focuses on research addressing the effects on materials properties and performance of exposure to the neutronic, thermal and chemical environments anticipated in the chambers of fusion experiments and energy systems. This research is a major element of the national effort to establish the materials knowledge base for an economically and environmentally attractive fusion energy source. Research activities on issues related to the interaction of materials with plasmas are reported separately. The results reported are the products of a national effort involving a number of national laboratories and universities. A large fraction of this work, particularly in relation to fission reactor irradiations, is carried out collaboratively with partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of fusion materials scientists to the broader fusion community, both nationally and worldwide.
36 MATERIALS SCIENCE↗
Progress on the Electron-Ion Collider
We will be reporting on the progress of the design and preparatory R&D for the Electron-Ion Collider.
Seryi, Andrei↗
SQMS Center Progress and Highlights and response to PAC recommendations
SQMS Center Progress and Highlights and response to PAC recommendations
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Industrial Assessment Center Program Final Progress Report
This final progress report details the work completed between Fiscal Years 2017 and 2021, including a no-cost extension partially through FY2022. Dr. Bryan Rasmussen served as the center director (2017-2022), with James Eggebrecht (2017-2022) and Heather Lewis (2021-2022) as Assistant Directors. The results in this report were compiled by Dr. Rasmussen from available records, and are correct to the best of our knowledge. The following should only be considered a partial listing of center activities.
32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
Progress in Genetic Algorithm Fitting of X-Ray Fluorescence Data for Absorption Spectroscopy of Liquid Surfaces
X-ray fluorescence (XRF) spectroscopy of liquid surfaces is a promising approach to elemental analysis of forensic samples. Elements in the mixture can be identified from the XRF data because chemical elements are associated with unique spectra. This report describes progress in the development of automated identification of unknown mixtures of elements from XRF spectra using a genetic algorithm (GA). The XRF spectra are measured at the Advanced Photon Source (APS) at the liquid-liquid interface during solvent extraction process. The usage of the GA is demonstrated and future implementation for related problems are then discussed.
47 OTHER INSTRUMENTATION↗
Improving Fission Products at CARIBU: Near Field Detection (Q2/FY24 Quarterly Progress Report)
We continue to make progress in the analysis of 111 Ag decay data to determine gamma-ray intensities with the aim of improving these intensities to below 1% precision. The correctness of detection efficiencies is integral to obtaining accurate and precise results. While Geant4 provides us with efficiencies for detection of a coincidence event of a beta-particle with a 96, 245, or 342 gamma-ray, as outlined in Figure 1, it is important that we validate these results with the efficiencies obtained from the experimental decay data.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Fusion Materials Semiannual Progress Report for the Period Ending December 31, 2023
This is the seventy-fifth in a series of semiannual technical progress reports on fusion materials science activity supported by the Fusion Energy Sciences Program of the U.S. Department of Energy. It covers the period ending December 31, 2023. This report focuses on research addressing the effects on materials properties and performance of exposure to the neutronic, thermal and chemical environments anticipated in the chambers of fusion experiments and energy systems. This research is a major element of the national effort to establish the materials knowledge base for an economically and environmentally attractive fusion energy source. Research activities on issues related to the interaction of materials with plasmas are reported separately. The results reported are the products of a national effort involving a number of national laboratories and universities. A large fraction of this work, particularly in relation to fission reactor irradiations, is carried out collaboratively with partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of fusion materials scientists to the broader fusion community, both nationally and worldwide.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗