Engineering topics

Brown, Dave

Publications and source records attributed to Brown, Dave.

9 records

DOE OSTI2024

Resolved resonance region evaluations of n+ 206,207,208 Pb for fast spectrum applications

Resolved resonance region evaluations of the major isotopes of natural lead, 206 Pb, 207 Pb, 208 Pb, have been per formed to support the development of Generation IV reactors. In this study, validation of nuclear data for lead fast reactors was performed with simulations of shielding benchmarks, integral critical benchmarks, and quasi-differential scattering measurements. Sensitivity analyses of these systems showed that elastic scattering reactions above 100 keV were the dominant reactions driving system performance. The resolved resonance regions (RRRs) of the lead isotopes extend past 100 keV, making the RRR an ideal starting point to evaluate lead cross sections. Since the R-matrix requires knowledge of bound, distant, and observed resonances, it was necessary to evaluate from 10 -5 eV up to the respective limit of the RRR. The 208 Pb RRR evaluation was extended to 1.5 MeV in order to obtain resonance parameters used to calculate new elastic scattering angular distributions up to 1.5 MeV. Resonance parameter uncertainties and covariance were generated using the R-matrix code SAMMY. The new RRR parameters show a direct improvement to the scattering kernel below 1.5 MeV which in turn greatly improves fast critical experiments over ENDF/B-VIII.0.

206Pb↗

DOE OSTI2023

Methodology for physics-informed generation of synthetic neutron time-of-flight measurement data

Accurate neutron cross section data are a vital input to the simulation of nuclear systems for a wide range of applications from energy production to national security. The evaluation of experimental data is a key step in producing accurate cross sections. There is a widely recognized lack of reproducibility in the evaluation process due to its artisanal nature and therefore there is a call for improvement within the nuclear data community. This can be realized by automating/standardizing viable parts of the process, namely, parameter estimation by fitting theoretical models to experimental data. This automation effort could greatly benefit from a synthetic data resource. This work leverages problem-specific physics, Monte Carlo sampling, and a general methodology for data synthesis to generate unlimited, labelled experimental cross-section data that is statistically indistinguishable to the observed data. Heuristic and, where applicable, rigorous statistical comparisons to observed data support this claim. The demonstration is based on/limited to transmission measurements at Rensselaer Polytechnic Institute (RPI) and energy-differential cross sections in the resolved resonance region (RRR). An open-source software is published alongside this article that executes the complete methodology to produce high-utility synthetic datasets. The goal of this work is to provide an approach and corresponding tool that will allow the evaluation community to begin exploring more data-driven, ML-based solutions to long-standing challenges in the field.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2023

Resolved Resonance Region Analysis of 206 Pb, 207 Pb, and 208 Pb for Next Generation Lead-Cooled Fast Systems

Recently, great interest has been generated in using lead as a coolant for fast neutron systems and as a result it is important to investigate the ENDF/B-VIII.0 isotopic evaluations that comprise stable le ad. To this end, resonance parameters for 206 Pb, 207 Pb, and 208 Pb were re-evaluated because their resolved resonance regions extend beyond 0.5 MeV meaning resonance parameters used in reconstructing cross sections and elastic scattering angular distributions impact fast systems. The impact of resonance parameters is demonstrated by the differences between the evaluations in predicting experimental results from the fully modeled RPI Quasi-Differential Scattering Experiment via MCNPv6.2. In addition, MCNP KCODE calculations of lead-sensitive fast spectra critical benchmarks showed variations of keff on average of 400 pcm, caused solely from differences in elastic scattering angular distributions in 208 Pb. Re-evaluation entailed fitting data with the program SAMMY.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2023

5-10 Years Cross-cutting Priorities on the Topic of Nuclear Data Covariances and Uncertainty Quantification for Users

The goal of this meeting was to draft a whitepaper on prioritized nuclear data covariance and uncertainty quantification needs impacting users for the next 5 to 10 years. These needs are described herein in an actionable context (i.e., a high-level plan is given to address them), and are feasible for the community to tackle the need (i.e., high-level idea of funding is provided). It should be noted that each of these proposed projects are ideal for training new nuclear data evaluators who are also integrated into application needs.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2022

Comparison of URR Implementations in GNDS Format [Slides]

LLNL implemented infrastructure to include treatment of URR in GNDS. There are two options to store URR probabilities: cross-sections pdf and ACE-like probability tables. Issues were found with both options during verification with criticality benchmarks. Projected future steps include resolving issues in the next year and adding criticality benchmarks sensitive to URR.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2021

Dr. Cecil Lubitz (1925–2021)

Dr. Cecil Lubitz passed away on March 5, 2021 at his home in upstate New York. A graduate of the Class of 1945 from the Naval Academy, Cecil served in the US Navy until 1947 after which he earned a MS in electrical engineering (1949) and a PhD in Physics (1960) from the University of Michigan. Following graduate school, Cecil came to work at Knolls Atomic Power Laboratory (KAPL) on applied nuclear physics in the Naval Nuclear Propulsion Program (NNPP). Cecil worked at KAPL for 54 years and had an impactful career with many substantial contributions to the NNPP, national and global nuclear data communities.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

DOE OSTI2019

PRECISE: Cutting Costs and Delays for Rooftop PV

Learn about the NREL-developed software Preconfiguring & Controlling Inverter Set-Points (PRECISE), which helps utilities identify optimal inverter modes and settings for distributed PV. PRECISE is a standalone system that allows utility engineers to seamlessly interconnect PV generation, significantly cutting the wait time and costs for customers.

14 SOLAR ENERGY↗

DOE OSTI2018

Estimating Radionuclide Activity in Surface Contamination for GTCC Activated Metal Waste Streams - 18236

The U.S. Nuclear Regulatory Commission's licensing requirements for land disposal of low-level radioactive waste (LLRW) in 10 CFR Part 61 classify LLRW wastes as Class A, B, C, or Greater-Than- Class C (GTCC). GTCC waste includes activated metals that are generated primarily by nuclear power reactors. Activated metals represent a significant volume (880 cubic meters) of GTCC wastes that may be generated as current commercial power reactors are decommissioned. Additionally, these wastes are expected to contain radionuclides that are very long-lived and are mobile in the environment (e.g., Tc-99 and I-129) as well as transuranic radionuclides that, while not as mobile as other radionuclides, have greater potential for health consequences should such radionuclides reach receptor locations in sufficient concentrations. Quantities of surface contamination on activated metals have typically been reported using a combination of assumptions, calculations, and measurements. For example, projections of future activity associated with surface contamination, or the surface activity, for the activated metals is dependent on assumptions made regarding fuel behavior (e.g., modern fuel performance is expected to be different from fuel performance in the 1970's). In this study, we examined published information to better understand how assumptions, calculations, and measurements used for estimating quantities of surface contamination on activated metals can influence the estimated quantities. The analysis in this report was performed to better understand how estimates for the activated metal inventory of GTCC metal could influence potential decisions regarding the siting and design of disposal facilities. It was found that the variability in surface contamination either measured or estimated was sufficiently large that characterization of the radionuclide inventory for GTCC activated metals, especially the transuranic radionuclides, is critically important for establishing the siting and design requirements for a disposal facility. Overly conservative assumptions for the inventory could significantly limit disposal options, whereas, overly optimistic assumptions with respect to the inventory could lead to a disposal facility that may not protect off-site receptors. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NASA NTRS1991

Identifying the unmodified structural characteristics using multiple modifications

This paper describes a procedure for estimating the free-free modal characteristics of a system by testing multiple constrained states. The procedure eliminates the influences of the constraints on the modal parameters and provides important information at the connection points. For very stiff or very flexible test articles, it is difficult to support the test article and to measure uncompromised modal parameters. The method described in this paper measures the forces and/or responses at constraint-connection points and uses a direct parameter estimation algorithm to calculate the system's free-free characteristics. These free-free characteristics retain the local information at the connection or boundary points, thereby including the important local high frequency residual effects in the modal model.

Barney, Patrick↗