Hyperbranched Polymer-Electrolyte Membrane Development for Carbon Dioxide Conversion to Solar Fuel
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36 MATERIALS SCIENCE↗
SEARCH · Engineering Papers
Results for “Fuel Development”
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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Developing the test conditions for the first fueled transients in the TREAT reactor
The restart of the Transient Reactor Test (TREAT) facility at Idaho National Laboratory, re-establishes a national in-pile testing capability for nuclear fuels in accident scenarios. The purpose of the first tests in TREAT are to study the response of nuclear fuel durring a reactivity initiated accident (RIA). The initial objective is to demonstrate the ability to create a desired enthalpy increase in a representative fuel test specimen over a desired time step and to better understand the uncertainty. The five test rods initially available for these irradiations are UO2-Zircaloy with standard Pressurized Water Reactor (PWR) geometry. The rods are 15 cm long with 9 cm of active fuel. The initial testing environment is dry helium. BISON fuel performance calculations were run to model the heat transfer during postulated transients. Based on those results energy deposition targets were selected around the range of observable phenomena in the testing environment. Reactor / experiment power coupling factors, step insertion size and transient clipping response times were then calculated using results from a RELAP point kinetics model. Calculated energy deposition targets are 150, 350, 650, 960, and 1300 J/gUO2. The energy coupling factor for the experiments was calculated to be ~1.5 J/gUO2-MJ. Two step insertion sizes were selected: a 0.6% ?k/k step for the 150 J/g transient and a 1.8% ?k/k step for the other transients. Clipping response times ranged from 1.3 seconds to unclipped transients. The experiments will be irradiated in the TREAT facility in the fall of 2018. The first transient will be the 150 J/g pulse with a 0.6% ?k/k step that is unclipped. Follow on tests may modify the reactor operating parameters based on results from previous transients. Any preliminary data available on the results of the transients at the time of the NUMAT Conference will be presented.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development
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Massey, Caleb↗
SAFETY AND PERFORMANCE ASPECTS IN THE DEVELOPMENT AND QUALIFICATION OF HIGH BURNUP NUCLEAR FUELS FOR WATER COOLED REACTORS
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Capps, Nathan↗
An Open-Source Coupling for Depletion During Fuel Cycle Modeling
Fuel depletion is an important aspect of fuel cycle modeling, allowing a user to account for how loaded fuel compositions affect in-core and spent fuel compositions and their related fuel cycle metrics. Therefore, multiple methods have been developed to account for depletion within fuel cycle simulations. This work adds to that list of methods by introducing an open-source coupling between C$\scriptsize{YCLUS}$ and OpenMC to perform fuel depletion during a fuel cycle simulation, called OpenMCyclus. This work explains the methodology of OpenMCyclus and presents a benchmark comparison between the performance of OpenMCyclus and another C$\scriptsize{YCLUS}$ archetype that uses recipes to define spent fuel compositions. In conclusion, the development of this coupling expands the functionalities possible through C$\scriptsize{YCLUS}$ by providing real-time fuel depletion that is reactor agnostic and open source.
C$\scriptsize{YCLUS}$↗
Developing the Irradiation Plan for U-10Mo LEU Fuel Qualification for the Advanced Test Reactor
The Department of Energy (DOE), National Nuclear Security Administration’s Office of Material Management and Minimization (M3) mission is to convert, remove, and dispose of vulnerable nuclear material located at civilian sites worldwide. As part of its mission, M3’s Office of Convert works around the world to convert research reactors and isotope production facilities to non-weapon-usable nuclear material, both domestically and abroad. In support of this, the Office of Convert is working with the Idaho National Laboratory (INL) to develop and qualify new fuels and technologies to support conversion efforts domestically and abroad. The INL also supports the Office of Convert by working on converting the Advanced Test Reactor (ATR) and the Advanced Test Reactor Critical (ATRC) from using High Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. To ensure the viability of ATR LEU fuel, the fuel system should meet a similar functional and operational envelope as the current HEU fuel. A series of irradiation tests of the U-10Mo LEU fuel system is required to support the qualification of the fuel system for use in the ATR and several other U.S. High-Performance Research Reactors (USHPRRs). These irradiation tests include: • Mini-Plate tests (MP-1, MP-2, and MP-ATR), • Full-Size Plate tests (FSP-1, and FSP-ATR), and • Element Tests (ET-1, ET-2, and ET-3). The MP tests will use multiple small-scale samples that will provide sufficient data across a wide variety of irradiation conditions to qualify the fuel. The FSP tests will use a small number of full-sized fuel plates to confirm the MP test results are representative of the prototypic plate geometry performance. The MP and FSP irradiation tests occur in ATR test locations. The ETs will use full-sized fuel elements located in ATR core driver positions to explore the full operating ranges of the ATR and other USHPRRs and to confirm that the MP and FSP test results are representative of the prototypic element geometry performance. The established testing functional and operational requirements of MP-1, MP-2, FSP-1, and ET 1 achieve the base fuel qualification needs of the USHPRRs, while the high-level purposes of MP-ATR, FSP ATR, ET 2, and ET-3 are focused on demonstrating U-10Mo fuel for ATR use.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Phosphoric acid fuel cell platinum use study
The U.S. Department of Energy is promoting the private development of phosphoric acid fuel cell (PAFC) power plants for terrestrial applications. Current PAFC technology utilizes platinum as catalysts in the power electrodes. The possible repercussions that the platinum demand of PAFC power plant commercialization will have on the worldwide supply and price of platinum from the outset of commercialization to the year 2000 are investigated. The platinum demand of PAFC commercialization is estimated by developing forecasts of platinum use per unit of generating capacity and penetration of PAFC power plants into the electric generation market. The ability of the platinum supply market to meet future demands is gauged by assessing the size of platinum reserves and the capability of platinum producers to extract, refine and market sufficient quantities of these reserves. The size and timing of platinum price shifts induced by the added demand of PAFC commercialization are investigated by several analytical methods. Estimates of these price shifts are then used to calculate the subsequent effects on PAFC power plant capital costs.
Lundblad, H. L.↗
Combustion of petroleum-based transportation fuels and their blends with biofuels: a new approach for developing surrogates and understanding the effects of blending
Accurate and versatile reaction mechanisms are necessary to simulate combustion of transportation fuels blended with biofuels for improving fuel efficiency, reducing fuel consumption and mitigating the formation and emissions of combustion products harmful to the atmosphere. This project involved a combined effort of simulation and experimentation of liquid fuel burning using a combustion configuration amenable to numerical modeling with a level of detail not previously achieved for blends of biofuels with gasoline certification and surrogate fuels. The configuration of an isolated droplet burning under conditions where gas transport arises solely from fuel evaporation was selected as the platform for experiments and numerical modeling. The spherical symmetry and one-dimensional gas transport that results enabled simulating the droplet burning process with an precedented level of detail. Processes associated with unsteady gas and liquid transport, formation of particulate and gaseous products, radiation, multicomponent phase equilibrium at the droplet surface and moving boundary effects from droplet evaporation, were incorporated in a single numerical framework. The numerical model was based on the open source code OPENSmoke++ (OS) adapted to incorporate the effects noted above. In addition to simulation, an experimental design was developed for the isolated droplet configuration to acquire the data needed for validating the numerical model. Several broad accomplishments of the project were the following: demonstrating generally excellent agreement between measured and simulated combustion parameters for the fuel blends examined that included mixtures of heptane and isobutanol as a model system, and surrogates comprised of up to seven miscible components mixed with ethanol or isobutanol as representative biofuel additives; using a new approach to validate reaction mechanisms of biofuel blends which incorporated fuel evaporation into the process along with developing an experimental design for acquiring data to compare with simulations; and showing that a wealth of information could be obtained on the combustion physics of biofuels from experiments requiring volumes on the order of only nanoliters at a time thus opening the way to evaluating biofuels synthesized by new processes early in development.
02 PETROLEUM↗
Design, fabrication, and testing of an external fuel (UO2), full-length thermionic converter
The development of a full-length external-fuel thermionic converter for in-pile testing is described. The development program includes out-of-pile performance testing of the fully fueled-converter, using RF-induction heating, before its installation in the in-pile test capsule. The external-fuel converter is cylindrical in shape, and consists of an inner, centrally cooled collector, and an outer emitter surrounded by nuclear fuel. The term full-length denotes that the converter is long enough to extend over the full height of the reactor core. Thus, the converter is not a scaled-down test device, but a full-scale fuel element of the thermionic reactor. The external-fuel converter concept permits a number of different design options, particularly with respect to the fuel composition and shape, and the collector cooling arrangement. The converter described was developed for the Jet Propulsion Laboratory, and is based on their concept for a thermionic reactor with uninsulated collector cooling as previously described. The converter is double-ended, with through-flow cooling, and with ceramic seals and emitter and collector power take-offs at both ends. The design uses a revolver-shaped tungsten emitter body, with the central emitter hole surrounded by six peripheral fuel holes loaded with cylindrical UO2 pellets.
Schock, A.↗
Identifying High Burnup LOCA Test Conditions to Support LOCA Testing
Presentation summarizing work done by INL and ORNL investigating loss-of-coolant accidents involving high burnup fuel. This includes developing LOCA test conditions for TREAT and SATS experiments and highlighting potential differences between nuclear and electrical heating LOCA experiments.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
FY17 end of year MARMOT materials model development update
This document summarizes the lower length scale progress made in FY17 in developing materials models for fuel performance modeling of oxide fuels and their implementation in the MARMOT code. The progress covers the development of a phase field recrystallization model for high-burnup structure formation in oxide fuels, a phase field model for studying stage-3 fission gas release in UO 2 , a phase-field model for irradiation-enhanced densification in UO 2 , a quantitative model for hydride morphology in Zirconium based cladding, and the calculation of hydrogen diffusivity under stress in various Zirconium based alloys as cladding candidates. Further development in the MARMOT code has been carried out as well to improve the multi-phase, multi-component phase field model, the representation of interfacial energy in the Kim-Kim-Suzuki model, and the description of interfacial stress. For most of the above, separated reports have been generated with detailed description. Here a brief summary is provided, with references pointing to the detailed reports to guide interested readers.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
In this study, a plate-type nuclear fuel consisting of a solid monolithic foil of U-10 wt. %Mo is under development for use in the United States' high-performance research reactors. In support of developing this fuel, the fuel has been fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an opportunity to evaluate postirradiation mechanical properties of the commercially fabricated fuel. Four-point bend testing was conducted on the irradiated U-10Mo samples to generate the fuel material properties, including the modulus of elasticity and the bending strength. Although the material behaves in a brittle manner due to the accumulated porosity, a general trend of strength and modulus reduction was found as fission density increases. The data produced was evaluated using both Weibull statistics and a modulus degradation model with recommendations provided.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Space shuttle electrical power generation and reactant supply system
The design philosophy and development experience of fuel cell power generation and cryogenic reactant supply systems are reviewed, beginning with the state of technology at the conclusion of the Apollo Program. Technology advancements span a period of 10 years from initial definition phase to the most recent space transportation system (STS) flights. The development program encompassed prototype, verification, and qualification hardware, as well as post-STS-1 design improvements. Focus is on the problems encountered, the scientific and engineering approaches employed to meet the technological challenges, and the results obtained. Major technology barriers are discussed, and the evolving technology development paths are traced from their conceptual beginnings to the fully man-rated systems which are now an integral part of the shuttle vehicle.
Simon, W. E.↗
Developing the User Experience for a Next Generation Nuclear Fuel Cycle Simulator (NGFCS)
This project made substantial progress on its original aim for providing a modern user experience for nuclear fuel cycle analysis while also creating a robust and functional next- generation fuel cycle simulator. The Cyclus kernel experienced a dramatic clari cation of its interfaces and data model, becoming a full- edged agent-based framework, with strong support for third party developers of novel archetypes. The most important contribution of this project to the the development of Cyclus was the introduction of tools to facilitate archetype development. These include automated code generation of routine archetype components, metadata annotations to provide re ection and rich description of each data member's purpose, and mechanisms for input validation and output of complex data. A comprehensive social science investigation of decision makers' interests in nuclear fuel cycles, and speci cally their interests in nuclear fuel cycle simulators (NFCSs) as tools for understanding nuclear fuel cycle options, was conducted. This included document review and analysis, stakeholder interviews, and a survey of decision makers. This information was used to study the role of visualization formats and features in communicating information about nuclear fuel cycles. A exible and user-friendly tool was developed for building Cyclus analysis models, featuring a drag-and-drop interface and automatic input form generation for novel archetypes. Cycic allows users to design fuel cycles from arbitrary collections of facilities for the rst time, with mechanisms that contribute to consistency within that fuel cycle. Interacting with some of the metadata capabilities introduced in the above-mentioned tools to support archetype development, Cycic also automates the generation of user input forms for novel archetypes with little to no special knowledge required by the archetype developers. Translation of the fundamental metrics of Cyclus into more interesting quantities is accomplished in the Cymetric python package. This package is speci cally designed to support the introduction of new metrics by building upon existing metrics. This concept allows for multiple dependencies and encourages building complex metrics out of incremental transformations to those prior metrics. New archetype developers can contribute their own archetype-speci c metric using the same capability. A simple demonstration of this capability focused on generating time-dependent cash ows for reactor deployment that could then be analyzed in di erent ways. Cyclist, a dedicated application for exploration of Cyclus results, was developed. It's primary capabilities at this stage are best-suited to experienced fuel cycle analysts, but it provides a basic platform for simpler visualizations for other audiences. An important part of its interface is the ability to uidly examine di erent slices of what is fundamentally a ve-dimensional sparse data set. A drag-and-drop interface simpli es the process of selecting which data is displayed in the plot as well as which dimensions are being used for
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Study of Rapid-Regression Liquefying Hybrid Rocket Fuels
A report describes experiments directed toward the development of paraffin-based hybrid rocket fuels that burn at regression rates greater than those of conventional hybrid rocket fuels like hydroxyl-terminated butadiene. The basic approach followed in this development is to use materials such that a hydrodynamically unstable liquid layer forms on the melting surface of a burning fuel body. Entrainment of droplets from the liquid/gas interface can substantially increase the rate of fuel mass transfer, leading to surface regression faster than can be achieved using conventional fuels. The higher regression rate eliminates the need for the complex multi-port grain structures of conventional solid rocket fuels, making it possible to obtain acceptable performance from single-port structures. The high-regression-rate fuels contain no toxic or otherwise hazardous components and can be shipped commercially as non-hazardous commodities. Among the experiments performed on these fuels were scale-up tests using gaseous oxygen. The data from these tests were found to agree with data from small-scale, low-pressure and low-mass-flux laboratory tests and to confirm the expectation that these fuels would burn at high regression rates, chamber pressures, and mass fluxes representative of full-scale rocket motors.
Zilliac, Greg↗
Dual-Pump CARS Measurements in the University of Virginia's Dual-Mode Scramjet: Configuration "A"
In this paper we describe efforts to obtain canonical data sets to assist computational modelers in their development of models for the prediction of mixing and combustion in scramjet combustors operating in the ramjet-scramjet transition regime. The CARS technique is employed to acquire temporally and spatially resolved measurements of temperature and species mole-fraction at four planes, one upstream of an H2 fuel injector and three downstream. The technique is described and results are presented for cases with and without chemical reaction. The vibrational energy mode in the heated airstream of the combustor was observed to be frozen at near facility heater conditions and significant nonuniformities in temperature were observed, attributed to nonuniformities of temperature exiting the heater. The measurements downstream of fuel injection show development of mixing and combustion, and are already proving useful to the modelers.
Cutler, Andrew D.↗
NMDQi Nuclear Materials Discovery and Qualification Initiative Conference Overview
The Nuclear Materials Discovery and Qualification Initiative (NMDQi) is designed to accelerate nuclear materials qualification to fulfill the promises of early and advanced reactor technologies as a safe, clean, and low-cost baseload energy. Materials development and qualification in the nuclear industry is by definition challenging due to stringent safety requirements, limited availability of specialized facilities for materials irradiation and testing, and the challenging high-temperature, high-radiation environment. NMDQi will establish tools and capabilities that will greatly accelerate the nuclear fuels and materials development process. These tools will provide both computationally informed insights and high-throughput infrastructure with the goal of completing qualification in a single pass. In this approach, materials must be fabricated with a range of properties of interest so that materials performance can be examined in parallel, rather than with multiple discrete specimens. Advanced manufacturing (AM) techniques, which can produce complex component geometries, microstructures, and compositions, are ideal. The improved process monitoring and control that AM can provide are ideal for ensuring and reducing material variability, which will be particularly important as standards committees pursue regulations for AM components. However, gaining these benefits requires overcoming the substantial barrier of qualifying AM processes and the resulting materials and components for supporting research campaigns and eventually nuclear service.
36 MATERIALS SCIENCE↗
Numerical Study of Stratified Charge Combustion in Wave Rotors
A wave rotor may be used as a pressure-gain combustor effecting non-steady flow, and intermittent, confined combustion to enhance gas turbine engine performance. It will be more compact and probably lighter than an equivalent pressure-exchange wave rotor, yet will have similar thermodynamic and mechanical characteristics. Because the allowable turbine blade temperature limits overall fuel/air ratio to sub-flammable values, premixed stratification techniques are necessary to burn hydrocarbon fuels in small engines with compressor discharge temperature well below autoignition conditions. One-dimensional, unsteady numerical simulations of stratified-charge combustion are performed using an eddy-diffusivity turbulence model and a simple reaction model incorporating a flammability limit temperature. For good combustion efficiency, a stratification strategy is developed which concentrates fuel at the leading and trailing edges of the inlet port. Rotor and exhaust temperature profiles and performance predictions are presented at three representative operating conditions of the engine: full design load, 40% load, and idle. The results indicate that peak local gas temperatures will result in excessive temperatures within the rotor housing unless additional cooling methods are used. The rotor itself will have acceptable temperatures, but the pattern factor presented to the turbine may be of concern, depending on exhaust duct design and duct-rotor interaction.
Nalim, M. Razi↗