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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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At least 127 records · Page 7
All sourcesNASA NTRSDOE OSTI
DOE OSTI2023

FY23 Status Report of the Activated Materials Laboratory at the Advanced Photon Source

The Activated Materials Laboratory (AML) is a new radiological facility located at the Advanced Photon Source (APS) in Argonne National Laboratory (ANL), adjacent to the high-energy x-ray microscopy (HEXM) beamline in the long beamline building (LBB) constructed under the APS-upgrade (APS-U) project. The AML is a centralized facility to facilitate the safe conduct of experiments on activated materials at the APS. This report provides an overview of the status of the AML as a Nuclear Science User Facilities (NSUF) partner user facility in preparation for the general user access in 2024 upon the commissioning of the APS-U beamlines. Specifically, details are provided regarding the laboratory's scope, functionality, components, operational blueprint, and data management approach. The plans on augmenting the instrumentation, refining operational procedures and developing a robust data management strategy for FY24 and beyond are also discussed.

43 PARTICLE ACCELERATORS↗
DOE OSTI2023

Status Report on Ion Irradiation Study of Ceramic Coating in Suppressing Fuel/Cladding Chemical Interaction

Advanced cladding is critical for the development of advanced nuclear reactors with enhanced performance in radiation tolerance and neutron transparency. It will ensure adequate thermal conductivity and mechanical stability of cladding base material, corrosion resistance and high temperature coolant compatibility of cladding surface. Finally, it provides chemical stability in the cladding inner wall against fuel/cladding chemical interaction (FCCI). An innovative cladding with a three-layer structure (i.e., a treated surface, a base material, and a treated inner-wall) promises to meet all the listed requirements. The initial work on innovative researching and developing these cladding materials seeks to demonstrate the effectiveness of a thin ceramic coating in suppressing FCCI through ion-irradiation. It consists of a study of Ce/TiN/Fe diffusion couples. This report provides an update on the status of ceramic-coating preparation and the testing of diffusion couple samples, the design of an ion-irradiation experiment, and characterization of the microstructure of a legacy-coupon sample coated with 1 µm of TiN and irradiated with 5 MeV Fe ions to 200 dpa at 500°C.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
NASA NTRS1979

Space Transportation System - Status report

A series of detailed illustrations present graphically the status of the STS. The Shuttle vehicle is compared to other expendable vehicles hitherto used by NASA, and data on the Shuttle's components and dimensions and weights are provided. Also presented is the mission profile for the Shuttle and the installation of Spacelab into the Orbiter. Illustrations cover the steps of the vehicle preparation for launch and a chart is given representing current plans for the launch of various payloads. Finally, the automated beam builder for aluminum beams, orbital test of a space machine for fabrication of structural elements or beams and a multibeam communications antenna, which can be used for very small receivers, are described.

Scherer, L. R.↗
NASA NTRS2000

Status Report on the Penn State RBCC Test Program

The status of the RBCC ejector mode research program at Penn State is reviewed. Recent hardware modifications and measurement system improvements are discussed, including the motivation for these changes. Results from a series of tests with a single thruster configuration at a chamber pressure of 200 psia and with an area ratio 3.3 nozzle are presented. These results indicate that the primary (rocket exhaust) and secondary (entrained air) flow streams mix much more rapidly than a previous test series with an area ratio of 6.0 nozzle. Finally, the plans for a test series with a twin thruster configuration are discussed.

Cramer, J.↗
DOE OSTI2020

Status Report on the Molten Salt Thermodynamic Database (MSTDB) Development (FY20)

The current status of the Molten Salt Thermodynamic Database (MSTDB) is reported. While a series of informational exchange meetings with Moten Salt Reactor (MSR) developers has given the NEAMS program insight into the systems of interest, the current effort is devoted to mining data already available in the literature for continued development of MSTDB. Many relevant systems have not been previously studied. Therefore, once the data from the literature is completely reviewed, curated, and used as inputs for MSTDB, new thermodynamic values will need to be generated using computational and experimental approaches.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2019

Status Report on the NuScale Module Developed in the Modelica Framework

This report has been prepared to give a status update on the current state of the NuScale reactor model in the Modelica framework. Current model development has led to the creation of a dynamic NuScale module in the Modelica language that operates under natural circulation and is consistent with design parameters set forth in the design certification documentation. Controllers have been developed that are consistent with controllers mentioned by NuScale and similar pressurized water reactor systems. Simulation results demonstrate the capability of said controllers to properly maintain their target parameters while preserving system values within reasonable bounds. Through the commencement of this work, the first generation of NuScale model in the Modelica M&S framework has been completed. This first generation is capable of recreating nominal design values laid forth in the public literature and accommodating transients down to 60% power. Future generations of the model will incorporate finer tuning on controllers to reduce oscillations seen with steam offtake and will include a more rigorous representation of components laid forth in the future work section.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2019

Shortening the Design and Certification Cycle for Additively Manufactured Materials by Improved Mesoscale Simulations and Validation Experiments: Fiscal Year 2019 Status Report.

This report outlines the fiscal year (FY) 2019 status of an ongoing multi-year effort to develop a general, microstructurally-aware, continuum-level model for representing the dynamic response of material with complex microstructures. This work has focused on accurately representing the response of both conventionally wrought processed and additively manufactured (AM) 304L stainless steel (SS) as a test case. Additive manufacturing, or 3D printing, is an emerging technology capable of enabling shortened design and certification cycles for stockpile components through rapid prototyping. However, there is not an understanding of how the complex and unique microstructures of AM materials affect their mechanical response at high strain rates. To achieve our project goal, an upscaling technique was developed to bridge the gap between the microstructural and continuum scales to represent AM microstructures on a Finite Element (FE) mesh. This process involves the simulations of the additive process using the Sandia developed kinetic Monte Carlo (KMC) code SPPARKS. These SPPARKS microstructures are characterized using clustering algorithms from machine learning and used to populate the quadrature points of a FE mesh. Additionally, a spall kinetic model (SKM) was developed to more accurately represent the dynamic failure of AM materials. Validation experiments were performed using both pulsed power machines and projectile launchers. These experiments have provided equation of state (EOS) and flow strength measurements of both wrought and AM 304L SS to above Mbar pressures. In some experiments, multi-point interferometry was used to quantify the variation is observed material response of the AM 304L SS. Analysis of these experiments is ongoing, but preliminary comparisons of our upscaling technique and SKM to experimental data were performed as a validation exercise. Moving forward, this project will advance and further validate our computational framework, using advanced theory and additional high-fidelity experiments.

36 MATERIALS SCIENCE↗
DOE OSTI2019

Status Report on Development of MARCH Module Designs

The Transient Reactor Test (TREAT) facility was constructed in the late 1950’s, provided thousands of transient irradiations before being placed in standby in 1994, and was restarted in 2017 in order to resume its crucial role in nuclear heated safety research. Advances in modern computational capabilities and a resurgence of interest in novel reactor technology have created an opportunity for emphasizing modern science-based and separate effects test capabilities at TREAT. An innovative approach to this type of testing leverages the relatively low radioisotope accumulation during brief TREAT irradiations by arranging small fresh fuel specimens in low activation hardware “modules” so that they can be easily extracted and shipped for examination within weeks. The concept was termed the Minimal Activation Retrievable Capsule Holder (MARCH) irradiation vehicle system, and its maturation began under a Lab Directed Research and Development (LDRD) project starting in fiscal year 2017. Within the first year of this project, enough design and predictive modeling had been performed to prove the principle and ascertain support from major direct-funded DOE fuel development programs including the Accident Tolerant Fuels (ATF) program that sponsored the first modern fueled test to be performed in TREAT using the MARCH system. Since the design was modular in nature, it was straightforward for other sources to adopt and mature viable test modules while the LDRD project continued concurrently for two more years in conceptualizing and demonstrating the viability of other innovative modules. Many of these modules were adopted for continued development and irradiation under the Advanced Fuels Campaign and other direct sources. This report summarizes the MARCH modules that were conceptualized, designed, and deployed to date with the primary aim of providing reference information to future experiment designers.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2020

FY20 Status Report on Photothermal Radiometry Development

This report documents FY20 progress in the development of a benchtop photothermal radiometry (PTR) instrument for the measurement of thermal diffusivity. A PTR system incorporating Off-Axis Parabolic (OAP) mirrors was designed and tested. Additionally, a novel analysis technique that accounts for systematic errors that affect measurement accuracy was implemented. Measurements on samples with a range of thermal diffusivities using the PTR setup along with the new analysis technique resulted in improved accuracy and repeatability. Areas for future development work are set forth.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Status Report on Photothermal Radiometry Development

Thermal transport properties such as thermal conductivity and diffusivity, are critical parameters in the development of improved nuclear fuels and components. It is well known that thermal transport properties change temporally and spatially due to dynamic microstructural evolution as a result of neutron irradiation. Laser based photothermal techniques are an ideal candidate for thermal properties measurement of irradiated materials because they are non contact, non destructive and can be performed remotely. In this report, we present the progress in the development of a photothermal radiometry (PTR) system to measure the thermal diffusivity of solid samples. The PTR technique measures the local temperature response from a modulated heat source by detecting the sample radiation heat flux. Initially, a well developed thermal wave analytical model was fit to the data to obtain the thermal diffusivity. However, systematic errors from the diffraction effect and non linearity issues resulted in thermal diffusivity measurements higher than literature values. These effects have been studied, an improved analytical model has been developed, and the physics behind the phenomena are still under investigation. A procedure for optimizing measurements from the benchtop system has been provided.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗