Engineering topics
Publications and source records attributed to Bowen, Doug.
This presentation details the discussion of agenda topics. Including the minutes from the last meeting and Membership. Additionally covered is ANS-8 and NCSCC ballots, ANS-8 participation report, and ANS-8 New and Old Business.
This presentation goes over the ORNL NCSP training and education support for Fiscal Year (FY) 2023. It includes a look at approved training and education tasks set up for FY2023. This lecture also covers revisions and updates to proposals and the LA-12808 LA-12808 Nuclear Criticality Safety Guide.
This presentation touches on the Radiation Safety Information Computational Center (RSICC). This Lecture provides general mission, statistics, and strategies. A general background is provided of the tool. Licensee agreements and export control agreements are discussed. The presentation finishes with a look at the most in demand and requested software packages.
This presentation details budget and spending details for Fiscal Year (FY) 2023 for ORNL NCSP. Highlights and accomplishments from ORNL are provided for FY2023.
This presentation is on the overview and status update of the Nuclear Criticality Safety Training and Pipeline Program. This lecture includes an introduction to the program, a program overview, and a status update at the end. Steps to complete moving forward are also provided.
This presentation includes a discussion of the agenda and ANS-8 and WG8 Chair Membership. The presentation continues with recent SC-8 & NCSCC Ballots and NCSCC Topics. This lecture concludes with reports from Working Group Chairs and any Old/New Business.
This presentation covers the Nuclear Criticality Safety Program (NCSP) training & education program. The presentation details the training courses offered by the NCSP and the NCSP training pipelines. Additionally, the presentation shows the Nuclear Criticality Safety (NCS) Education Training (NCSET) modules along with new capabilities and new courses. This lecture finishes up with some concluding remarks.
This presentation was created to highlight several pertinent topics and reports to introduce into the forum. This presentation covers membership along with the recent SC-8 & NCSCC ballots. Topics discussed include the ISO TC85/SC5/WG8 standards activity with a report from D. Bowen. Additionally, a NCSCC activity report by L. Wetzel was received. Along with reports from working group chairs. Finally, any Old/New Business was introduced.
This lecture covers the Nuclear Criticality Safety Repository (NCSR), Radiation Safety Information Computational center (RSICC), and Non-destructive Assay (NDA) program. The lecture provides information on the Fiscal year of 2022 and various phases of the NCSR Program and NDA. Further background information is provided for the RSICC and operations summary.
This presentation is on Oak Ridge National Labatory (ORNL) Nuclear Criticality Safety Program (NCSP) training and education support for Fiscal Year 2022. This lecture explains the approved training and education tasks for fiscal year 2022. Additional training developments for 2022 are covered.
This presentation covers the Oak Ridge National Laboratory (ORNL) Nuclear Criticality Safety Program (NCSP) fiscal year 2022 budget summary. This presentation includes charts and graphs on budget spending and spending details for the 2022 fiscal year.
As part of the nuclear data evaluation and validation cycle, the ENDF/B-VIII.0 cross-section library released in 2018 requires testing to determine areas of improvement and deterioration. Previous work by the authors investigated the performance of 16 O, 56 Fe, and 63,65 Cu cross sections, with this study acting as an extension of the prior work. In addition to the isotopes and nuclear criticality safety benchmarks of interest to the prior work, benchmarks from the International Criticality Safety Benchmark Evaluation Project Handbook were selected for their k eff sensitivity to 1 H, C, 58,60 Ni, 182,183,184,186 W, 235,238U, or 239 Pu cross sections and were modeled in the SCALE code system maintained by Oak Ridge National Laboratory. In total, 253 benchmark configurations were selected for their sensitivities and modeled using SCALE 6.2.4 Criticality Safety Analysis Sequences (CSAS) continuous-energy Monte Carlo k eff calculations. This collection includes and expands upon the 99 benchmarks in the prior work. The AMPX-processed ENDF/B-VIII.0 library was decomposed into individual ENDF/B-VIII.0 datum libraries for each isotope of interest. Doing so allowed for the individual substitution of an ENDF/B-VIII.0 cross section in the place of ENDF/B-VII.1, determining isotope-specific effects of ENDF/B-VIII.0 relative to ENDF/B-VII.1. Full library calculations with entirely ENDF/B-VII.1 data or entirely ENDF/B-VIII.0 data were also executed. As a measure of performance, the average relative deviation was determined as the ratio of the deviation between calculated and experimental keff to the propagated calculational and experimental uncertainty. With calculated full library and isotope-specific ENDF/B-VIII.0 k eff ’s, an optimized combination of data libraries was estimated and confirmed with SCALE calculations. This showed that reverting 239 Pu, 58 Ni, 16 O, and 65 Cu cross sections to ENDF/B-VII.1 resulted in improved performance relative to the full ENDF/B-VIII.0 library. Across all 253 benchmarks, the average relative deviation was 1.29σ for the full ENDF/B-VII.1 library, 1.17σ for the full ENDF/B-VIII.0 library, and 0.97σ for the optimized combination. The reversion of 239 Pu, 58 Ni, 16 O, and 65 Cu cross sections to ENDF/B-VII.1 in the 99 benchmarks of the prior work resulted in further improved experimental agreement compared to the previously reported improvement from 16 O and 65 Cu alone. Therefore, it is suggested that applications with significant sensitivities to 239 Pu, 58 Ni, 16 O, and 65 Cu consider their choice of nuclear data library.
A range of fuel arrays has been examined for both fuel types and representative arrays were selected. Temperature dependent calculations were performed to show the performance of the arrays. Modification to the SPRF/CX facility has been proposed to aid SNL staff in the execution of temperature dependent experiments.