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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 469 records · Page 26
All sourcesNASA NTRSDOE OSTI
DOE OSTI2011

Documentation for DOE/SC/NP Quadrennial Low Energy Nuclear Physics (LENP) Review

Research at LLNL is primarily directed towards satisfying its principal missions in international security, fusion energy, and US nuclear security. Towards this end, a core LLNL strategy has been to advance fundamental scientific understanding to succeed in its purpose, and to recruit and develop a skilled workforce for the future. Research conducted in the Physics Division at LLNL is primarily focused on bringing the highest quality science to bear on LLNL programs to achieve broad success in its overall mission. In this regard, the ―applied-science‖ missions at LLNL are actually quite well-aligned with the fundamental-science research aims of the Office of Science. We aim to perform research for DOE/SC/NP at LLNL that has the greatest leverage towards answering fundamental problems in nuclear science -- both at the forefront of fundamental science and important to the nation’s security. Towards this end, LLNL brings unique capabilities, resources, and skills to bear on the most scientifically challenging endeavors of the DOE/SC/NP mission and enhances the training of the nuclear science workforce in general. LLNL is a world leader in cost-effective high-performance computing, has a broad collection base for Laboratory Directed Research and Development (LDRD), and an excellent track record in solving multi-disciplinary and engineering problems.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2013

Documentation of a Linked-Population Viability Model to Evaluate Recovery Options for Snake River Fall Chinook Salmon

We developed an age- and life-history based population viability analysis model for linked populations of fall Chinook salmon (LPVA). LPVA was designed to quantify the costs and benefits of re-establishing access to an upstream spawning area using managed reconnection options such as hatchery stocking and translocation. The model incorporates stochasticity in the age at which salmon return to spawn, sex ratio, juvenile life history, and survival rates. Response variables include the proportion of replicate populations that persisted for 80 y (roughly 20 generations), the linked population’s growth rate, λ, time to extinction and summaries of population sizes including average female spawner abundance, final female spawner abundance, and total female abundance. This report attempts to provide a complete model description, including simulation of management options and options for simulating forward with a joint distribution of parameters based on their likelihoods with respect to historical data. Intermediate results illustrating the Bayesian approach to identifying poorly-known parameters are reported here. LPVA simulates reconnection of linked populations by representing management processes such as trapping of adults migrating upstream at two dams and juveniles migrating downstream, and hatchery operations for one or two hatcheries. The purpose of the model is to support efforts to recover the threatened Snake River fall Chinook salmon ESU by evaluating population viability using existing spawning areas with and without a hatchery and to assess the potential costs and benefits of programs to re-establish an upstream spawning area.

Jager, Henriette (Yetta) I.↗
DOE OSTI2013

Compilation of Criteria and Summaries from B332 Seismic Evaluations for the Initial Scoping Document Release of the HS-45 LLNL Audit, February 7, 2013

This study consists of separate evaluations of Increment I, Increment III and the Plenum Building. The analysis was limited to the structural components of these structures and did not include architectural features, components nor mechanical or electrical equipment or systems. The seismic analysis was an elastic dynamic analysis following the UCRL-15910 guidelines.

58 GEOSCIENCES↗
DOE OSTI2013

nuSTORM Costing document

Detailed costing of the nuSTORM conventional facilities has been done by the Fermilab Facilities Engineering Services Section (FESS) and is reported on in the nuSTORM Project Definition Report (PDR) 6-13-1. Estimates for outfitting the primary proton beam line, the target station, the pion capture/transport line and decay ring are based on either experience from existing Fermilab infrastructure (NuMI) or is based on the detailed costing exercises for DOE CD-1 approval for future experiments (mu2e and LBNE). The detector costing utilized the Euronu costing for the Neutrino Factory Magnetized Iron Neutrino Detector (MIND), extrapolations from MINOS as-built costs and from recent vendor quotes. Costs included all manpower and are fully burdened (FY2013 dollars). The costs are not escalated, however, beyond the 5-year project timeline, since a project start for nuSTORM is unknown. Escalation can be estimated from various models (see Figure 1). LBNE has used the Jacob’s model to determine their cost escalation.

Bross, Alan D.↗
DOE OSTI2013

Documenting Dual-Column Experiment with Mini-SHINE Solution

Argonne National Laboratory (Argonne) is assisting SHINE Medical Technologies (SHINE) in developing a production method and recovery and purification processes for molybdenum 99 (Mo-99) using an accelerator-driven, subcritical target consisting of an aqueous uranyl-sulfate solution. An integral part of the process is the development of a column for the separation and recovery of Mo-99, followed by a concentration column to reduce the product volume from 15–25 L to <1 L prior to entry into the low-enriched uranium (LEU)-Modified Cintichem purification process. Argonne has developed plant-scale column designs for the initial Mo-recovery column and the concentration column.

Stepinski, Dominique C.↗
DOE OSTI2014

Requirements Document for the Redesign of the DIM-based Diagnostics Transport and Handling System at the National Ignition Facility (NIF)

The National Ignition Facility (NIF, Figure 1) is the world’s leading user research facility for inertial confinement fusion. Diagnostic instruments that collect data from the experiment shots are transported around the facility using a series of disjointed, suboptimal transport and handling (T&H) subsystems that compromise user efficiency and ergonomics. Significant time savings and improvements to the diagnostic exchange process could be realized by designing a new transport and handling system that minimizes the hand-offs between T&H subsystems, reduces operator hassle and ergonomic strain, and improves the long-term maintainability of the system. In contrast to the current system – which employs several manually-operated carts and containers to transport the diagnostic, dock it to its destination, and install it – the new diagnostic transporter integrates the contamination container with the transport cart and provides a dynamic range of adjustability to interface with its destination. This single transporter has the requisite maneuverability, height adjustability, and fine adjustment capabilities without any rigging transactions to support contaminated diagnostic transport and handling at the alignment station and Equatorial and Polar DIMs. A remote-controlled user interface device allows operators a more hands-off experience that reduces ergonomic strain and improves safety. Assuming the cost is not prohibitive, diagnostic storage will be accomplished by simply stowing the transporter in its lowest position in the designated area of NIF. This concept for a new diagnostic transport and handling system would be better aligned with the core values of NIF: safety, quality, and reliability.

42 ENGINEERING↗
DOE OSTI2014

Preliminary Feasibility Assessment of Integrating CCHP with NW Food Processing Plant #1: Modeling Documentation

The Pacific Northwest National Laboratory (PNNL) has launched a project funded by the Bonneville Power Association (BPA) to identify strategies for increasing industrial energy efficiency and reducing energy costs of Northwest Food Processors Association (NWFPA) plants through deployment of novel combinations and designs of variable-output combined heat and power (CHP) distributed generation (DG), combined cooling, heating and electric power (CCHP) DG and energy storage systems. Detailed evaluations and recommendations of CHP and CCHP DG systems will be performed for several Northwest (NW) food processing sites. The objective is to reduce the overall energy use intensity of NW food processors by 25% by 2020 and by 50% by 2030, as well as reducing emissions and understanding potential congestion reduction impacts on the transmission system in the Pacific Northwest.

Bonneville Power Association↗
DOE OSTI2014

Letter Report Documenting Progress of Second Generation ATF FeCrAl Alloy Fabrication

Development of the 2 nd generation ATF FeCrAl alloy has been initiated, and a candidate alloy was selected for trial tube fabrication through hot-extrusion and gun-drilling processes. Four alloys based on Fe-13Cr-4.5Al-0.15Y in weight percent were newly cast with minor alloying additions of Mo, Si, Nb, and C to promote solid-solution and second-phase precipitate strengthening. The alloy compositions were selected with guidance from computational thermodynamic tools. The lab-scale heats of ~ 600g were arc-melted and drop-cast, homogenized, hot-forged and -rolled, and then annealed producing plate shape samples. An alloy with Mo and Nb additions (C35MN) processed at 800°C exhibits very fine sub-grain structure with the sub-grain size of 1-3μm which exhibited more than 25% better yield and tensile strengths together with decent ductility compared to the other FeCrAl alloys at room temperature. It was found that the Nb addition was key to improving thermal stability of the fine sub-grain structure. Optimally, grains of less than 30 microns are desired, with grains up to and order of magnitude in desired produced through Nb addition. Scale-up effort of the C35MN alloy was made in collaboration with a commercial cast company who has a capability of vacuum induction melting. A 39lb columnar ingot with ~81mm diameter and ~305mm height (with hot-top) was commercially cast, homogenized, hot-extruded, and annealed providing 10mm-diameter bar-shape samples with the fine sub-grain structure. This commercial heat proved consistent with materials produced at ORNL at the lab-scale. Tubes and end caps were machined from the bar sample and provided to another work package for the ATF-1 irradiation campaign in the milestone M3FT-14OR0202251.

2nd generation ATF FeCrAl alloy↗
DOE OSTI2012

The Use of MOX Fuel in the United States: Bibliography of Important Documents and Discussion of Key Issues

Although this paper provides a short history and discussion of some of the important issues pertaining to WG-MOX, the primary focus of the paper is to provide a useful bibliography of resources pertaining to weapons-grade MOX fuel use in LWRs. Therefore, not all aspects of MOX use were reviewed in this paper. Sandia National Laboratory and other investigators have performed significant work in the United States on severe accident source terms for MOX fuel cycles in comparison with LEU fuel cycles. Sandia’s source term reports indicate that due to some off-setting factors, the actual source terms between MOX and LEU are not significantly different despite the inventory differences. However, those source terms were not used to perform an explicit consequence evaluation to draw a conclusion on the overall integrated risk. Even though there are inventory differences and there is the potential for differences in the source term for MOX fuel, the overall uncertainties in the accident progression, fission product release/retention, source term and risk analyses would indicate that there is no significant difference between MOX and LEU fuel. In addition, recent research shows that current guidelines for fission product release (NUREG-1465) are significantly conservative (by a factor of 2). The National Academy of Sciences has stated: “We believe, further, that under these circumstances no important overall adverse impact of MOX use on the accident probabilities of the LWRs [light water reactors] involved will occur, if there are adequate reactivity and thermal margins in the fuel, as licensing review should ensure, the main remaining determinants of accident probabilities will involve facts not related to fuel composition and hence unaffected by the use of MOX rather than LEU Fuel (NAS, 1995).”

Bevard, Bruce Balkcom↗
DOE OSTI2014

Perform Tests and Document Results and Analysis of Oxide Layer Effects and Comparisons

During the initial feasibility test using actual used nuclear fuel (UNF) cladding in FY 2012, an incubation period of 30–45 minutes was observed in the initial dry chlorination. The cladding hull used in the test had been previously oxidized in a dry air oxidation pretreatment prior to removal of the fuel. The cause of this incubation period was attributed to the resistance to chlorination of an oxide layer imparted by the dry oxidation pretreatment on the cladding. Subsequently in 2013, researchers at the Korea Atomic Energy Institute (KAERI) reported on their chlorination study [R1] on ~9-gram samples of unirradiated ZirloTM cladding tubes that had been previously oxidized in air at 500oC for various time periods to impart oxide layers of varying thickness. In early 2014, discussions with Indefinite Delivery, Indefinite Quantity (IDIQ) contracted technical consultants from Westinghouse described their previous development (and patents) [R2] on methods of chemical washing to remove some or all of the hydrous oxide layer imparted on UNF cladding during irradiation in light water reactors (LWRs) . Thus, the Oak Ridge National Laboratory (ORNL) study, described herein, was planned to extend the KAERI study on the effects of anhydrous oxide layers, but on larger ~100-gram samples of unirradiated zirconium alloy cladding tubes, and to investigate the effects of various methods of chemical pretreatment prior to chlorination with 100% chlorine on the average reaction rates and Cl2 usage efficiencies.

Korea Atomic Energy Institute (KAERI)↗
DOE OSTI2014

Battery Lifetime Analysis and Simulation Tool (BLAST) Documentation

The deployment and use of lithium-ion (Li-ion) batteries in automotive and stationary energy storage applications must be optimized to justify their high up-front costs. Given that batteries degrade with use and storage, such optimizations must evaluate many years of operation. As the degradation mechanisms are sensitive to temperature, state-of-charge (SOC) histories, current levels, and cycle depth and frequency, it is important to model both the battery and the application to a high level of detail to ensure battery response is accurately predicted. To address these issues, the National Renewable Energy Laboratory (NREL) has developed the Battery Lifetime Analysis and Simulation Tool (BLAST) suite. This suite of tools pairs NREL’s high-fidelity battery degradation model with a battery electrical and thermal performance model, application-specific electrical and thermal performance models of the larger system (e.g., an electric vehicle), application-specific system use data (e.g., vehicle travel patterns and driving data), and historic climate data from cities across the United States. This provides highly realistic long-term predictions of battery response and thereby enables quantitative comparisons of varied battery use strategies.

25 ENERGY STORAGE↗
DOE OSTI2012

Industrial Sector Energy Efficiency Modeling (ISEEM) Framework Documentation

The goal of this study is to develop a new bottom-up industry sector energy-modeling framework with an agenda of addressing least cost regional and global carbon reduction strategies, improving the capabilities and limitations of the existing models that allows trading across regions and countries as an alternative.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗
DOE OSTI2015

Progress to Date on Developing the NUSAM Methodology Document

The same basic steps occur when evaluating the physical protection of nuclear or radiological material in transport against theft or sabotage as are needed for protecting nuclear facilities and nuclear material in use or storage. There are some notable distinctions, however. There are limited layers of protection around material when in transport so that the analysis focuses more on scenario analysis than for fixed sites which may require formal path analysis if the facility has some complexity. In many respects, ground transportation security is more challenging than security at a fixed site. Operation in the public domain is frequently required and the same degree of access limitation is not possible as it is in a protected fixed site. Because of these differences, response force personnel in transit play a more dominant role in the security of a mobile system than they do for a fixed site. In all cases, however, the system time delay that is required to provide the response force the time to react must be provided primarily by transportation vehicle technology elements.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗