Course: 25953 TSQP - Design, Development, Implementation [Slides]
The purpose of this course is to help you begin to design, develop, and implement training courses.
96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗
SEARCH · Engineering Papers
Results for “KNOWLEDGE MANAGEMENT”
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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Building Model Calibration: Validation of GridLAB-D Thermal Dynamics Modeling
This report investigates how well GridLAB-D’s house model characterizes the thermal dynamics of buildings given the overpredicted diurnal electric load swing observed in the Distribution System Operation with Transactive (DSO+T) study. This study seeks to validate GridLAB-D’s house model by calibrating it to data from the well-instrumented Pacific Northwest National Laboratory Lab Homes in Richland, WA. The datasets chosen included multiple pre-cooling and pre-heating testing periods where the indoor air temperature was allowed to float over a multi-hour length of time to mimic diurnal behavior. The multi-season calibrations were evaluated by comparing the heating/cooling electric power, indoor air temperature, and the rise/decay time during temperature float periods with Lab Homes data. The default GridLAB-D assumptions for latent load fraction, air heat capacity, mass heat capacity, window-to-wall-ratio, overall envelope conductance (assumed as NORMAL thermal integrity level), and solar heat gain coefficient were compared with the calibrated model to confirm when the default assumptions were adequate and the impact of calibration on the accuracy of modeling the thermal dynamics of homes.
32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
Hands-On Experimental Training [Slides]
Training provided includes: Nuclear Criticality Safety Fundamentals, Sub-Critical "Hands On" Demonstration, Hand-Stacking and Remote Approach to Critical Using the Planet Assembly, Flattop Free-Run Demonstration, and Godiva-IV Critical Assembly Demonstration.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
LANL Critical Benchmark Comparison Study and Subsequent Revision for Cases Involving LEU and MIX
As part of an international collaboration within the DOE Nuclear Criticality Safety Program (NCSP), LANL is involved in a comparison study to quantify differences in k-effective results from neutron transport simulations of critical benchmark experiments. The DOE NCSP Mission and Vision details the activity in which the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) leads the study with LANL, ORNL, and LLNL to compare results of various neutron transport codes and nuclear data libraries for ICSBEP benchmarks held in common by the entities. The task statement from the DOE NCSP Five-Year Execution Plan is given as: "The proposal is for IRSN to lead a new intercomparison based on the MORET code with the latest JEFF-3.3 data and ENDF/B-VIII.0 data, when available, using their existing comprehensive selection of 2,714 benchmarks and collate their results together with those from LLNL (COG), LANL (MCNP) and ORNL (SCALE). Due to the large number of benchmarks involved, this effort is envisioned to take three years with an additional year for IRSN to complete a summary report. The benchmark development will be performed independently to minimize modeling errors through discovery and resolution of discrepant results. A summary report will be generated (led by IRSN) to document the results of this study." This report documents results obtained for revisions made to cases involving Intermediate Enriched Uranium (IEU) and a mixture of Pu and Uranium (MIX), with a focus on the changes made to LANL benchmarks modeled with MCNP6 using ENDF/B-VII.1 nuclear data that appeared to have discrepant results when compared with results of other codes. Feedback was used to pinpoint review of particular benchmark input files and to revise them when necessary. This report documents the results of review and revision of specific benchmarks highlighted as possibly discrepant in the comparison study. In addition, there is an effort tied to this work involving collaboration between LANL XCP and NCS Divisions in the development of a shared review/revision procedure and use of a new benchmark repository.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
The History of Monte Carlo and MCNP at Los Alamos [Slides]
The Monte Carlo method for radiation particle transport has its origins at LANL dating back to the 1940’s. The creators of these methods were Drs. Stanislaw Ulam, John von Neumann, Robert Richtmyer, and Nicholas Metropolis. Monte Carlo methods for particle transport have been driving computational developments since the beginning of modern computers; this continues today. In the 1950’s and 1960’s, these new methods were organized into a series of special-purpose Monte Carlo codes, including MCS, MCN, MCP, and MCG. These codes were able to transport neutrons and photons for specialized LANL applications. In 1977, these separate codes were combined to create the LANL Monte Carlo N-Particle (MCNP) radiation particle transport code. In 1983, MCNP3 was released for public distribution to the Radiation Safety Information Computational Center (RSICC). MCNP6.3 will be released late in 2021. Each year, LANL has ~100 MCNP new users and RSICC ~1250 new licenses distributed. This talk will review the Los Alamos history of the development of the modern Monte Carlo method and MCNP.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
MCNP6.3 Workshop [Slides]
This workshop presentation revisits several new features of MCNP6.2 and tools. Additionally, it offers a preview of the new features and improvements included in the upcoming MCNP6.3 code release that are most relevant to the nuclear radiation protection and shielding communities.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Work Scope for Receiving Subcritical Assembly Fuel [Slides]
Abstract not provided.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
American Nuclear Society Standards Committee Subcommittee 8 Meeting [Slides]
The agenda was as follows: Discussion of Agenda, membership, Winter Meeting ANS-8 Subcommittee Minutes, ISO TC85/SC5/WG8 Standards Activity Report - D. Bowen, Nuclear Criticality Safety Consensus Committee (NCSCC) Activity Report - L. Wetzel, Reports from Working Group Chairs, and Old/New Business.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Comparison of ISO and ANSI/ANS Nuclear Criticality Safety Standards [Slides]
This paper provides a high-level comparison between the international and domestic nuclear criticality safety (NCS) standards, as requested by members of the Nuclear Criticality Safety Division. Currently, there are 18 enacted American National Standards Institute (ANSI)/American National Standards (ANS) standards, and 1 ANSI/ANS standard, in progress. There are 11 NCS standards from the International Organization for Standardization (ISO), Technical Committee 85 (TC85) on Nuclear Energy, Subcommittee 5 (SC5) on Nuclear Fuel Cycle, Working Group 8 (WG8). NCS standard revisions are in progress for both standards organizations. The key differences between the ISO TC85/SC5/WG8 and ANSI/ANS-8 consensus NCS standards are summarized. The hard work done by the ANS-8 and WG8 volunteers allows for applicable, high-quality consensus standards for use by the NCS community. This paper defines the current status of each ANSI/ANS and ISO standard, the work in in progress, the revisions/amendments in progress, and WG8/ANS-8 non-standard business in progress. A forthcoming paper will compare the development process for ISO and ANSI/ANS standards.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Action Sheet 66: Neutron Induced Nuclear Data Cross Section Measurements at JRC-Geel [Slides]
Experiments for 142 Ce have been performed in 2019. The data are reduced to cross section and transmission, respectively. Report for 142 Ce experiments is in preparation. Data analysis is underway, and the evaluation should be finalized by the end of 2020. 90 Zr sample is produced, but experiments planned for 2020 are delayed due to COVID-19.
142Ce↗
The DOE Nuclear Criticality Safety Program (NCSP) [Slides]
This presentation provides an overview of the Nuclear Criticality Safety Program (NCSP), including its mission, vision, program element activities, current work, recent accomplishments, and budget/funding information.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Needs and Development of the ENDF α-particle Sub-library: Measurements, Evaluation, Modeling, Format, and Simulation [Slides]
Abstract not provided.
07 ISOTOPE AND RADIATION SOURCES↗
Updates to the R -matrix Analyses of 233,235 U and 239 Pu; Updates to 63,65 Cu Evaluations in the RRR+URR; Current Status of 16 O Evaluation Up to 6 MeV [Slides]
Abstract not provided.
07 ISOTOPE AND RADIATION SOURCES↗
NEFCD All-Hands Meeting – Overview of Nuclear Criticality, Radiation Transport, and Safety (NCRTS) Section [Slides]
Topics for the meeting were as follows: Safety Minute, High-level Overview of NCRTS, Overview of NCRTS Groups (Radiation Transport, Nuclear Data, and Nuclear Criticality Safety), and Question and Answer.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Experiments for SINBAD: Evaluation of Oak Ridge Health Physics Research Reactor Operation Data for CAAS Benchmark Creation [Slides]
This report was a real information preservation and dissemination work with a lot of legacy content that was found and used. There was an abundance of uncertainty, discrepancy, and contradictory information. Yet, a detailed, functional SCALE model was built, and the benchmark created is useful for shielding and CAAs validation work. Sulfur fluence C/E ratios are large (2 to 5), so different benchmark metrics were studied. Neutron fluence, element 57 dose, and other dosimetry responses at 3 meters C/E ratios are below 1.5 for bare and steel configurations. Additional promising metrics as dose per unit fluence and steel shield attenuation were computed.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Business Continuity, Cybersecurity, and Backup Control Center: Standards, References, and Recommendations (White Paper)
This Whitepaper provides an overview and synopsis of relevant standards for Control Center, Cyber Security and Continuity of Operations for electric power utilities. It also provides suggestions and recommendations for the outline of a cybersecurity plan and a business continuity plan, and suggests training and certification opportunities for both cybersecurity and business continuity.
24 POWER TRANSMISSION AND DISTRIBUTION↗
Advanced Reactors Campaign and NCERC [Slides]
Abstract not provided.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Modernization efforts for the R-Matrix code SAMMY [Slides]
This presentation details modernization efforts for the R-Matrix code SAMMY. It provides an overview of SAMMY, modernization and maintenance goals, modernization accomplishments, covariance data, SAMMY API development, as well as future plans.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗