A Minimally Supervised Event Detection Method (AHFE 2021 presentation).
Abstract not provided.
Hoffman, Matthew John↗
SEARCH · Engineering Papers
Results for “Sammy”
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.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
SAND Report Guide
This SAND Report Guide offers support to authors, technical writers, principal investigators, and others involved in the process of creating, formatting, or refining a SAND Report. It details what you need to know before you begin compiling a SAND Report, directs you to the SAND Report templates, outlines the order of elements in a SAND Report, and explains what to do when your report is completed and ready for Review and Approval and subsequent distribution. Supporting information is provided in the appendix, such as where to get technical assistance, trademarks, Microsoft Word, and equations.
96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗
140,142 Ce Neutron Cross Section Resolved Resonance Region Evaluation [Slides]
ORNL has completed new RRR evaluations for 140,142 Ce. A lack of integral measurements made validation difficult, but the difference from Kadonis values suggests that more investigation of capture cross section is warranted. The complete file (with updated File2 and File32) has been submitted to NNDC repository for inclusion in next release of ENDF. A sponsor report publication is in progress.
07 ISOTOPE AND RADIATION SOURCES↗
Recent Developments in the Nuclear Data Processing Code AMPX [Slides]
This presentation provides overviews of ENDF and GNDS reading in AMPX, AMPX covariance processing updates, thermal scattering law updates, and data libraries for SCALE 6.3.0.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Updates and Validation for the n+ 63,65 Cu Cross Sections [Slides]
The RRR and URR parameters for 63,65 Cu have been optimized to transmission and capture data. Several data sets have been newly incorporated in this evaluation. The angular distribution parameters have been adopted from differential measurements, as was done in ENDF/B-V. The performance of this evaluation in the integral benchmark calculations is favorable, and the validation is ongoing.
07 ISOTOPE AND RADIATION SOURCES↗
Including inverse channel in n+ 16 O R-matrix evaluation and analysis on the 35 Cl(n,p) reaction channel [Slides]
Abstract not provided.
07 ISOTOPE AND RADIATION SOURCES↗
Reproducibility and Optimization Techniques for Evaluated Data in the Resolved Resonance Region: Set of Dysprosium Isotopes [Slides]
Abstract not provided.
07 ISOTOPE AND RADIATION SOURCES↗
Nuclear Data Needs from Nuclear Criticality Safety Program’s Perspective and Beyond [Slides]
Abstract not provided.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
RECENT AMPX developments [Slides]
This presentation covers recent AMPX developments. Presentation highlights include the news of AMPX being openly available, link to source and configure options are included. The interconnections between AMPX and Generalized Nuclear Database Structure (GNDS) are additionally highlighted as well.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Process Capability Study on the Volume Manufacturing of a Complex Rotating Automotive Component in Laser Powder Bed Fusion Additive Manufacturing
Oak Ridge National Lab (ORNL) and Ford Motor Company used an AddUp FormUp 350 to print a turbo wheel geometry to show feasibility of laser powder bed fusion (L-PBF) additive manufacturing (AM) in producing cost-effective components for automotive industries. L-PBF AM has potential to disrupt traditional manufacturing techniques by introducing novel materials and geometries that cannot otherwise be produced. Fundamental challenges associated with L-PBF include limitations on printing overhang geometries and resulting surface finish. In this collaboration, ORNL and Ford partnered with AddUp to show the viability of using L-PBF for an AM design turbine wheel while reducing as-fabricated surface roughness. A cost model associated with mass production was produced to analyze benefits of pursing LPBF AM compared to investment casting.
36 MATERIALS SCIENCE↗
Embodied Carbon Resource Navigator
The Embodied Carbon Resource Navigator is a guide to help architects, engineers, designers, contractors, and those who want to reduce their embodied carbon impact make more informed design decisions for buildings. The guide is a compilation of embodied carbon resources, organized by experience level to direct the user to the necessary resources.
29 ENERGY PLANNING, POLICY, AND ECONOMY↗
Advancements in nuclear data evaluations in the unresolved resonance region [Slides]
Minimal updates to current capabilities (SAMMY/AMPX) and to the ENDF format are proposed to include threshold reaction for outgoing charged-particle channels in the URR formalism. If average resonance parameters are reported, probability tables for newly defined reactions channels may be needed, implemented, and tested. Nuclear data evaluation of n+ 35 Cl reactions can be considered the best case to apply the proposed updates.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Characterization of the Multi-Coincident Bismuth Germanate Oxide Spectrometer at the Nuclear Counting Facility
A multi-detector γ-ray spectroscopy system including 3 high-purity germanium (HPGe) detectors has been developed at the Nuclear Counting Facility at Lawrence Livermore National Laboratory. This system operates not only in conventional singles γ-ray detection mode but also incorporates features like coincidence and anti-coincidence techniques. These advanced detection modes can significantly enhance the system’s sensitivity, making it a powerful tool for isotope identification and quantification, especially for complex samples with high background and overlapping peaks. In this re port, we present a comprehensive performance characterization of the Multi-Coincident Bismuth Oxide Spectrometer (MCBOS) using a variety of sample types, including 60 Co, 48 Sc, and mixed fission product samples. Each sample provides unique tests for the MCBOS capabilities. Additionally, a GEANT4 model of the MCBOS has been generated to aid with the characterization of the system.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
R-matrix Evaluation of the 15 N Compound System for Criticality Safety Analysis [Slides]
This presentation covers motivation and Introduction, experimental Data Considered in the Analysis, R-Matrix Analysis and Model Details and Selection of Critical Benchmark Experiments.
Nuclear Criticality Safety Program (NCSP)↗
Evaluation of Neutron Reactions on 139 La for Criticality Safety Analyses [Poster]
139 La is a stable fission product that contributes to fission product credit in criticality safety analyses. In order to improve reaction covariances for the sake of sensitivity analyses, the evaluation of neutron reactions on 139 La was performed to support the Nuclear Criticality Safety Program (NCSP).
ENDF↗
Joint Sample Analyses of Nuclear Forensic Materials Provided by the Republic of Kazakhstan: U. S. Laboratory Results
This document serves as an interim report to summarize sample analyses performed by Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL) on a series of five nuclear forensics samples provided by the Institute of Nuclear Physics (INP) in the Republic of Kazakhstan. The sample set contains four uranium oxide powders and one low-enriched uranium fuel pellet. The samples were provided as part of a broader collaboration that involved a set of joint sample analyses conducted by INP and the US National Laboratories. The joint analyses are being conducted using well-developed analytical plans. These activities are designed to support the advancement of nuclear forensic science and capacity building in all three institutes in both countries. This report builds upon an earlier preliminary summary of the joint interactions and will be augmented by a final report. The final report will summarize the results and value of all sample analyses performed at the three institutes (INP, LLNL, and LANL). The final report will also provide an intercomparison of the results, analytical methods and best practices employed, as well as outline future collaborative nuclear forensics activities that are being developed in the Kazakhstan region.
and nuclear chemistry↗
Using radiochemistry to diagnose fuel-ablator mix in inertial confinement fusion studies at the National Ignition Facility: measurement of Tc/Mo isotopic ratios for the Pushered Single Shell campaign
The development of radiochemical measurement techniques as a diagnostic for fusion experiments at the National Ignition Facility enables a new method for assessing fuel-ablator mix and the impact of this mix on capsule performance. Diagnosing capsule mix in internal confinement fusion studies is difficult due to the small spatial scales (10s of µm) and short-time frames (100s of ps) over which the mix typically evolves in these experiments. For the Pushered Single Shell campaign, radiochemical measurements on debris collected from fusion experiments can be used to determine isotopic ratios of activation products, particularly 96g Tc/ 99 Mo and 95g Tc/ 99 Mo, to provide vital information on nuclear reactions in the burning plasma that can inform simulations that seek to understand the degree of capsule-fuel mix and the impact on the capsule performance. These radiochemical measurements have been conducted regularly since November 2023 providing data on a range of capsule designs and neutron yields. Data from eight NIF experiments is presented, the measured 96g Tc/ 99 Mo and 95g Tc/ 99 Mo range from (0.5–5) × 10 –4 to (0.3–3) × 10 –4 , respectively. The development of radiochemical diagnostics aids in understanding and optimizing the design of fusion experiments, providing unique and valuable insights into capsule behavior and directly measuring fuel-ablator mix.
and nuclear chemistry↗