Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “DOUG”

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.

At least 595 records · Page 33

Interim Report on FY22 ORNL A709 Welding Research and Testing of Production Welds in Support of Developing ASME A709 Code Case Data Package

As part of the Alloy 709 ASME Code Case development effort under the Advanced Reactor Technologies (ART) Program, this work covers the development of the technical basis for weld fabrication and weld qualification of Alloy 709. This report summarizes the Alloy 709 welding research conducted at Oak Ridge National Laboratory (ORNL) in FY 2022. Two new production welds were fabricated on two commercial heats of Alloy 709 of different phosphorus (P) levels using Alloy 709 filler metal with P content less than 20 wppm with gas tungsten arc welding (GTAW). Both production welds successfully passed ASME Section IX weld qualification tests, and this concludes the Alloy 709 welding procedure development to scale up to 2-in thick plates. In FY 2022, we also demonstrated the success in welding of high P commercial Alloy 709 plates with weld wires having higher P content at 30 wppm. A test weld fabricated with the 30 wppm weld wire on the first commercial heat (140 wppm P) passed all weld qualification tests without issues. Additionally, experiment setup and testing procedure of the circular patch weldability test has been developed, for evaluating the P effect in weld wire on solidification cracking susceptibility of Alloy 709 weld, with the preliminary results summarized in this report. Research on further relaxing the P level restriction beyond 30 wppm are planned in FY 2023. The preliminary cross-weld creep tests results continue to show little or no creep strength reduction relative to the base metal.

36 MATERIALS SCIENCE↗

Technology and Innovation Roadmap

This Technology and Innovation Roadmap (Roadmap) presents a comprehensive and integrated assessment of the technology elements related to maintaining the River Protection Project (RPP) baseline, reducing risk, and providing opportunity for improvement. These elements contribute to achieving successful completion of the Hanford Site tank waste cleanup mission. Key near-term U.S. Department of Energy (DOE), Office of River Protection (ORP) RPP mission needs with respect to the next 5 years are identified and prioritized. This Roadmap is used to assist with planning near-term scope to address technology development priorities in fiscal year 2023 (FY23).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

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↗

Brief Overview of the NCSP [Slides]

The mission of the NCSP is to provide sustainable expert leadership, direction, and the technical infrastructure necessary to develop, maintain, and disseminate the essential technical tools, training, and data required to support safe, efficient fissionable material operations within the Department of Energy. The vision of the NCSP is a continually improving, adaptable, and transparent program that communicates and collaborates globally to incorporate technology, practices, and programs to be responsive to the essential technical needs of those responsible for developing, implementing, and maintaining nuclear criticality safety.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Volume 10: Flow Test Facilities

Adding additional flow testing facilities has been considered as part of the High Flux Isotope Reactor (HFIR) Sustaining and Enhancing Neutron Science (SENSe) Initiative at Oak Ridge National Laboratory (ORNL) to support HFIR operations and experiments. This prospect has prompted many ideas and discussions regarding potential features, configurations, locations, and applications for the facilities. A working group of ORNL staff members was formed in fiscal year 2022 to recommend one or more configurations to best support future HFIR operations and scientific capacities and to develop order-of magnitude cost estimates and timing. The ideas discussed in this report include options ranging from upgrading existing small-scale testing facilities to building a full-scale HFIR mockup for detailed thermohydraulic testing and fuel assessment.

07 ISOTOPE AND RADIATION SOURCES↗

Workshop on Sustainable Aviation Fuel-Use Research Opportunities

On February 15-16, 2022, the U.S. Department of Energy’s (DOE’s) Vehicle Technology Office (VTO) within Energy Efficiency and Renewable Energy (EERE) convened a workshop to assess the end-use research opportunities for Sustainable Aviation Fuels (SAF). This report summarizes the proceedings and findings of the workshop, which the U.S. Department of Energy’s Argonne National Laboratory hosted as a virtual event. During these two half-days, invited members of national laboratories, industry, government, and academia connected virtually to share perspectives on SAF research needs for improving end-use adoption.

09 BIOMASS FUELS↗

Nuclear Criticality Safety Repository, Radiation Safety Information Computational Center (RSICC), & NDA Program [Slides]

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.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

TREAT Cask Stand Drawings for Unlimited Use

This report contains drawings of the HFEF-15 Cask stand in the TREAT Reactor Building (MFC-720) and the Cask Stand Tower on the south wall of the TREAT High Bay. Public release is sought so these can be sent to DOD-SCO and their contracted companies looking at options for fueling the PELE reactor prior to demonstration in the DOME or elsewhere at INL.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Status of ORNL TSL evaluations [Slides]

This presentation is on the status of Oak Ridge National Laboratory (ORNL) Thermal Scattering Evaluation (TSL) evaluations. A focus of this presentation centers on the preliminary work on Teflon and Polyethylene evaluation validation.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ORNL NCSP FY 2022 Budget Summary and Highlights [Slides]

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.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

ORNL NCSP Training and Education Support for FY2022 [Slides]

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.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Status of ORNL TSL evaluations [Slides]

This lecture provides details on the status of ORNL TSL evaluations. Main sections include modeling of concrete, updates of polyethylene evaluation, and initial transmission measurements at Oak Ridge National Labatory (ORNL). The presentation Conclusions show that literature review and initial modeling of concrete components have been performed. INS and transmission measurements of concrete and hydrated cement have been also planned. Additionally, A new TSL library for Polyethylene was created and submitted to NNDC and development for a new transmission capability at ORNL is underway.

36 MATERIALS SCIENCE↗