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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 newest development version of MCNP (post-6.2.1), the α-eigenvalue solver has undergone some changes. A new approach for computing was added alongside the current ACODE algorithm. This document will briefly discuss the changes made by this modification, both in the current ACODE and in the new algorithm, as well as the new capabilities this method provides.
We worked on improving the representation of biological processes in the biogeochemical module of Earth System Models. In particular we developed a new modeling capability for the marine nitrogen cycle. The technical report gives a brief overview of the publications that resulted from the award.
The miniature fuel (MiniFuel) irradiation experimental design at Oak Ridge National Laboratory (ORNL) enables irradiation testing of small fuel specimens in the High Flux Isotope Reactor (HFIR) in support of the Advanced Fuels Campaign (AFC). The first set of irradiated MiniFuel specimens will be available for post-irradiation examination this year. X-ray computed tomography (XCT) has been established as a viable method for determining the post-irradiation volume of the specimens and the corresponding swelling due to irradiation. The work described herein explored the resolution capabilities in using XCT to determine the volume of representative MiniFuel geometries. Strategies for optimization of the parameters used during the measurement and the uncertainty of the method according to specimen geometry are reported.
A variety of fast neutron imaging simulations and measurements were performed to investigate the spatial resolution and small feature detection capability of a version of the Oak Ridge National Laboratory fast neutron tomographic imaging system. Two image quality indicators were examined: (1) a variety of long steel pins embedded axially in the interior of a polyethylene cylinder, and (2) a variety of short steels pins embedded radially in the surface of a polyethylene cylinder. Measurements demonstrated detectability of about 3 mm. Further data analysis may show improved detection performance and allow a more precise determination of the spatial resolution. Our current simulation code takes only partial consideration of the DT generator neutron production spot size, with neutron production effectively originating at a single point. Simulations showed that features less than 2 mm should be detectable with an improved generator. Our current ING-27 DT generator has a neutron production spot size of about 3.5 mm, which appears to be the limiting factor at present. Generators with spot sizes as small as 1 mm are commercially available. Higher-power, small–spot size associated particle generators are at the prototype stage and are expected to be commercially available soon.
This report is a proposal preparation and defense for the Department of Homeland Security (DHS). It discusses capabilities for opioid screeners, previous successes, and suggestions for future use.
This report details laboratory and field capabilities in long-term monitoring of legacy waste sites.
The supported research was motivated by a need to understand a robustly observed degradation of core electron thermal confinement in NSTX that is believed to be caused by beam- driven, high frequency, core-localized compressional (CAE) and global (GAE) Alfvén eigenmodes. The supported research sought to understand the role of CAEs and GAEs in the confinement degradation and to experimentally investigate leading hypotheses for the underlying mechanism. The supported research also sought to advance a predictive capability for CAEs and GAEs, which is potentially necessary for accurate prediction of Te profiles in future ST devices. Under the supported research, significant progress was made toward both goals. Multiple opportunities were realized to validate codes for predicting the characteristics of CAEs and GAEs, including the leading model for CAE and GAE stability, implemented in the Hybrid kinetic code HYM, and the CAE3B Hall MHD eigenmode code. Measurements of CAE and GAE mode internal structure and amplitude were obtained in NSTX and DIII-D (as part of the NSTX-U/DIII- D Collaborative Research National Campaign in 2017), contributing to this validation effort. In many cases, these measurements were firsts of their kind. These measurements also contributed to tests of the leading hypotheses for the role of CAEs and GAEs in core thermal confinement degradation in NSTX. The results of the tests cast doubt on these hypotheses, although questions remain. Activities under the supported research also included other firsts. For instance, experimental evidence was obtained for CAE-KAW mode coupling in NSTX (one of the hypothesized energy transport mechanisms) and a beam density threshold was observed for a CAE in DIII-D.
How does a structure fail in an explosion? Is there an engineering design opportunity to mitigate the effects of a blast? These are questions that may be addressed with simulation; however, a computational simulation capability to answer these questions must include developments in material physics modeling and numerical algorithms that we believe are possible, but do not yet exist. This LDRD project proposes to develop the physics models and computational approaches to create a computational simulation approach to answer these physics and engineering questions.
We describe progress developing the Device for Indirect Capture Experiments on Radionuclides (DICER) on flight path 13 at the Lujan Center at the Los Alamos Neutron Science Center (LANSCE). This capability is being developed to tightly constrain neutron-capture cross section on short-lived radioactive nuclides of high importance to weapons-program sponsors via neutron total cross section measurements on the same nuclides. In this report, we describe progress in this endeavor during October 2018 through September 2019.
The mission of the US Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to develop, apply, deploy, and support state-of-the-art predictive modeling and simulation tools for the design and analysis of current and future nuclear energy systems. This is accomplished by using computing architectures that range from laptops to leadership-class facilities. The NEAMS Workbench is a new initiative that will facilitate the transition from conventional tools to high fidelity tools by providing a common user interface for model creation, review, execution, output review, and visualization for integrated codes. The Workbench can use common user input, including engineering-scale specifications that are expanded into application-specific input requirements through the use of customizable templates. The templating process can enable multifidelity analysis of a system from a common set of input data. Additionally, the common user input processor can provide an enhanced alternative application input that provides additional conveniences over the native input, especially for legacy codes. Expansion of the integrated codes and application templates available in the Workbench will broaden the NEAMS user community and will facilitate system analysis and design. Current and planned capabilities of the NEAMS Workbench are detailed here.
As droughts and changing climate patterns cause water shortages and potential water system disruptions, there is a growing need for water resilience, which is the ability to withstand, adapt to, and recover from disruption. The Environmental Protection Agency’s (EPA) report on Water Audits and Water Loss Control for Public Water Systems [EPA, Water Audits and Water Loss Control for Public Water Systems] states that average water loss in distribution systems is 16%, 75% of which is lost through leaks. Commercially available leak detection technologies were researched to identify current capabilities and average use costs, including operation and management (O&M) considerations, how to operate the devices, and current limitations. It was found that the cost-effectiveness of leak detection technologies is not ubiquitous across all systems. Factors that must be taken into account include the size of the water system, the amount of water use, and the currently known water losses in the system. A variety of technologies are summarized to give water managers a basic understanding of the tools available to them, and help enable them to make a more informed choice of how to reduce water losses in their water systems.
The DOE Office of Nuclear Energy (DOE-NE) cybersecurity program would like to expand the use of the Human Systems Simulation Laboratory to include capabilities for cybersecurity research and development. Specifically, the introduction of hardware-in-the-loop (HITL) simulation of nuclear power plant architecture into the HSSL will enable researchers and nuclear utilities the ability to identify impacts generated by sophisticated hostile cyber adversaries to identify the consequences of simulated potential attack vectors, and to develop solutions for detecting or preventing these cyber attacks.
UCLA led the efforts of the US on Fusion Nuclear Science and Technology (FNST) for the past 35 years and is the recognized leader of FNST research. UCLA research focuses on identifying and characterizing the key FNST issues with high scientific content, performing pioneering experiments and advancing modelling capabilities, and has led many pioneering domestic and international studies on FNST that greatly advanced the FNST field. Examples of major achievements include our leadership and research work in: FINESSE: Seminal contribution to defining the FNST issues and research approach APEX: High power density concepts including free surface liquid walls and divertors FNSF/VNS: Need for and definition of FSNF conceived and pioneered by UCLA US ITER Test Blanket Program: Defined the test program with international community and options for US participation US-JA JUPITER and TITAN research collaborations: First of a kind research on Molten salt MHD and other advanced functional materials UCLA-EUROfusion collaboration: construction of a first-of-a-kind multiple effect LM-MHD-Thermofluid test facility The achievements and the associated publications during the current grant period of 2/1/2017 to 01/31/2019 are summarized in this final report for the following research areas: First experiments on a First-of-a-Kind Multiple-effect Facility in Liquid Metal MHD Research Self-Generated Stress Evolutions in Ceramic Breeder Material System Thermomechanics Integrated Model for Tritium Transport and Permeation Predictions FESS Liquid Wall Study The people working on the project during this period are listed in Section III. There is no unexpended funds at the final budget period.
The ECP/VTK-m project is providing the core capabilities to perform scientific visualization on Exascale architectures. The ECP/VTK-m project fills the critical feature gap of performing visualization and analysis on processors like graphics-based processors. The results of this project will be delivered in tools like ParaView, Vislt, and Ascent as well as in stand-alone form. Moreover, these projects are depending on this ECP effort to be able to make effective use of ECP architectures.
A Capability Pillar is a broad, multidisciplinary area of technical strength that is required for execution of enduring programs and in which the Laboratory needs to maintain robust national/ international leadership and depth. More meaningfully, a Pillar is an ongoing construct for planning how we combine competencies to address big, difficult, persistent, and endemic problems.
Los Alamos National Laboratory (LANL) is the location of the Los Alamos Neutron Science Center (LANSCE). The presentation outlines the various components and capabilities at LANSCE.
This simple Microgrid Design Toolkit (MDT) use case will provide you an example of performing microgrid sizing by identifying the types and quantities of technology to be purchased for use in a microgrid. It will introduce basic principles of using the MDT microgrid sizing capability by comparing the results of two microgrids in two different markets. Please reference the MDT User Guide (SAND2017-9374) for detailed instructions on how to use the tool.
In this STTR program, QuesTek Innovations LLC, a leader in the field of computational materials design, partnered with the University of Minnesota to expand its computational Materials by Design ® technology by developing a “design toolkit” that enables the subsequent design and development of novel, multilayer, multicomponent, high-performance T/EBC for CMC turbine components. In order to develop a T/EBC system capable of meeting all of the design requirements, this toolkit will then be applied to address critical technical challenges including developing a higher-temperature oxidation-resistant bondcoat while addressing thermo-chemical/mechanical compatibility between coating layers. QuesTek led the overall STTR program with the long-term objective to design and develop unique compositions to enable the application of T/EBCs for higher temperature gas turbines. Prof. David Poerschke from University of Minnesota (UMN) conducted experiments to support the design of high performance T/EBCs based on his expertise in the area of high-temperature oxidation and the environmental protection challenges involved in implementing SiC-CMC technology in gas turbine systems.