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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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Precise 3D reactor core calculation using spherical harmonics and discontinuous Galerkin finite element methods
We study the use of P{sub N} method in angle and discontinuous Galerkin is space to solve 3D neutron transport problem. P{sub N} method consists in developing the angular flux on truncated spherical harmonics basic. In this paper, we couple this method with the discontinuous finite elements in space to obtain a complete discretization of the multigroup neutron transport equation. To investigate its precision, the method was applied to Takeda and C5G7 benchmark problems. These calculations point out that the proposed P{sub N}-DG method is capable of producing accurate solutions in small computational time, and that it is able to handle complex 3D geometries. (authors)
Transition Core Modeling for Extended Enriched, Accident Tolerant Fuel Using PARCS/Polaris
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Phase 1 Specifications and preliminary sensitivity analyses of the OECD-NRC liquid metal fast reactor core thermal-hydraulics benchmark
The developments in wire-wrapped fuel bundle thermal-hydraulics research have become increasingly diverse and this makes comparisons across studies difficult. This paper describes an ongoing benchmark that will address this issue by directly comparing computational results with experimental data from two unique wire-wrapped thermal-hydraulic facilities. Preliminary subchannel sensitivity / uncertainty analyses show largely expected behavior for the presented cases, where rod diameter and friction factor show the greatest sensitivities to geometrical perturbations. Guidelines for computational fluid dynamics evaluations have been prepared and highlight the need for consolidated modeling strategies. (authors)
Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels
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Comparisons of Nodal Diffusion and Whole-Core Transport Methods for Multiple Cycles of a Small Light Water Reactor
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Adjoint Driven Ex-Core Response Estimation in a PWR with Thermal Feedback
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Fast-Spectrum Critical Assemblies with a Pb-HEU Core Surrounded by a Copper Reflector
The Department of Energy invests tens of millions of dollars each year to develop the next generation of nuclear engineering modeling & simulation (M&S) tools. These M&S tools are used to analyze advanced reactor designs and the safety of current nuclear operations. As computers become more powerful, we are able to enhance resolution in our calculations. This improved resolution is taking us to a point where the limitations of simulation capability are in the quality of data, including our ability to quantify the uncertainty and sensitivity of the data. In order to accurately model systems of interest, the industry must improve key nuclear data measurements and our confidence of how well we understand the data. Thus, M&S tools need evaluated and quality-assured experimental data for validation purposes. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) compiles benchmark experiment data in a handbook that can be used by criticality safety engineers to validate computer codes and cross-section libraries at nuclear facilities. Both critical and subcritical experiments are included in the handbook. Figure 1 organizes all the benchmark evaluations that have been performed by the isotope of interest, in this case Pb, and the neutron energy within the system. Compared to other isotopes of interest for nuclear applications, there are few benchmark evaluations for Pb systems. This has caused the latest nuclear cross-section libraries to over/underestimate changes in the neutron population compared to experimental results. Therefore, this evaluation fills an important knowledge gap in benchmark evaluations.
In-Core Neutron Flux, Temperature, and Pressure Instrumentation for the WIRE-21 Experiment in the High Flux Isotope Reactor
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Investigation of Point-Contact Strategies for CFD Simulations of Pebble Bed Reactor Cores
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Plutonium-238 Production Sensitivity and Validation Studies Continued: Effects of Core Component Compositions
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SCALE Analysis of the HTR-PROTEUS Core 4 Pebble-Bed Benchmark
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Multi-millijoule hollow-core fiber compression of short-wave infrared pulses to a single cycle
Approaches for efficient pulse compression can enable dramatic increases in the available peak power, as well as enable the generation of isolated attosecond X-ray pulses. Achieving high compression ratios for longer wavelength drivers has, however, been challenging. We present the compression of few-cycle 2.1 µm central wavelength short-wave infrared laser pulses to 6.9 fs with 2.35 mJ pulse energy at a 10 kHz repetition rate. Electric field resolved measurements reveal a single cycle light field oscillation. With a carrier-envelope-phase stability of 131 mrad and average power fluctuations below 1 %, the system constitutes an excellent light source for strong-field experiments and attosecond physics.
Ultrafast 1 MHz vacuum-ultraviolet source via highly cascaded harmonic generation in negative-curvature hollow-core fibers
Not Available
Computed Tomography Scanning and Geophysical Measurements of the T.R. McMillen 2 Core
Carbon Storage TRS.
Core Characterization of the Whipkey ST1 Well - Marcellus Shale
CT and geophysical data of the Marcellus from the Whipkey ST 1 well in Greene Co PA API No: 37-059-24715 latitude 39.9000020N, longitude -80.0199970W Please see the following technical report for further details. Crandall, D.; Moore, J.; Brown, S.; Mackey, P.; Carr, T. Computed Tomography Scanning and Geophysical Measurements of the Marcellus Formation from the Whipkey ST 1 Well NETL-TRS-X-2018; NETL Technical Report Series; U.S. Department of Energy, National Energy Technology Laboratory: Morgantown, WV, 2018; p 54.
Discrete measurements of the least horizontal principal stress from core data: An application of viscoelastic stress relaxation
Data used in JGR Solid Earth manuscript.
P-V-T measurements of Fe3C to 117 GPa and 2100 K: Implications for stability of Fe3C phase at core c
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