Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Completeness”

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 1,297 records · Page 72
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Completion of the ATR LEU Conversion Conceptual Design

The review period was initiated with a kick-off meeting held October 26, 2017. The design review package (Table 1) was presented and reviewer responsibilities and expectations discussed. Presentations by the project team included a project overview and summaries of the neutronic, thermal, and structural analysis. The participants were instructed to review the design in accordance with their knowledge area and submit written comments, questions, or deficiencies (CQDs). The CQDs were received from reviewers on form 412.13. Their comments were resolved and acceptance signatures were received.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2019

Complete Status Report Documenting the Processing, Microstructure and High-Temperature Mechanical Properties of the Nanostructured Ferritic Alloy OFRAC

This report provides a summary of the new nanostructured ferritic alloy, OFRAC (Oak Ridge Fast Reactor Advanced Fuel Cladding), that was developed for the advanced sodium fast reactor fuel cladding and core internals. The composition of OFRAC, which is Fe-12Cr-1Mo-03.Ti-0.3Nb + 0.3Y2O3 (wt. %), was chosen to achieve high temperature strength as well as high temperature creep performance and swelling resistance requirements that past structural materials such as austenitic stainless steels and ferritic/martensitic steels, i.e. HT-9, are not suitable as SFR cladding materials. The mechanical alloying procedures were described for producing OFRAC and the detailed characterization studies revealed uniformly distributed, high concentration of Y-Ti-O enriched oxide particles, or nanoclusters. The Nb addition that was intended to sequester interstitial C and N that are commonly introduced as contamination during ball milling of powder was found to be very effective in forming coarse size Nb carbonitrides along with excess Ti that removes these interstitial elements from the bcc-Fe matrix of OFRAC. The tensile tests on the OFRAC in the extruded condition showed excellent balance in strength and ductility from room temperature to 800°C. Both the microstructure and tensile properties were not significantly degraded after annealing the extruded OFRAC samples for 8 h at 1050°C and 1150°C. The latter temperature is ~76% of the melting point of OFRAC. These results demonstrated the stability of the microstructure and tensile properties to extremely high temperatures. The thermal creep resistance at elevated temperatures and stresses was investigated using strain rate jump testing. The results showed that OFRAC possessed high stress exponents at high stresses and temperatures of 550°C, 600°C, 700ºC and 800°C. This thermal dependence of minimum creep rate indicates that OFRAC will show quite low creep rates at higher temperatures and stresses compared to HT-9 and stainless steels. These significant improvements indicate that the NFA OFRAC alloy is a compelling and viable choice for sodium fast reactor fuel cladding.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Physics-Informed Machine Learning for Predictive Turbulence Modeling: Towards a Complete Framework

Although increased availability of computational resources has enabled high-fidelity simulations (e.g., large eddy simulations) of turbulent flows, the Reynolds-Averaged Navier–Stokes (RANS) models are still the dominant tools in industrial applications. However, the predictive capabilities of RANS models are limited by large model-form discrepancies due to the Reynolds stress closure. Recently, a Physics-Informed Machine Learning (PIML) approach has been proposed to learn the functional form of Reynolds stress discrepancy in RANS simulations based on available data. It has been demonstrated that the learned discrepancy function can be used to improve Reynolds stresses in new flows where data are not available. However, due to a number of challenges, the improvements are only demonstrated in the Reynolds stress prediction but not in corresponding propagated quantities of interest (e.g., velocity field). In this work, we investigate the prediction performance on the velocity field by propagating the corrected Reynolds stresses in PIML approach. To enrich the input features, an integrity basis of invariants is implemented. The fully developed turbulent flow in a square duct is used as the test case. The discrepancy model is trained on flow fields from several Reynolds numbers and evaluated on a duct flow at a higher Reynolds number than any of the training cases. The predicted Reynolds stresses are propagated to velocity field via RANS equations. Numerical results show excellent predictive performances in both Reynolds stresses and their propagated velocities, demonstrating the merits of the PIML approach in predictive turbulence modeling.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗
DOE OSTI2020

Overview of research completed with funding from the SciDAC CSPM project (Final Technical Report)

The Center for the Study of Plasma Microturbulence was a SciDAC project managed by the Office of Fusion Energy Sciences in the US Department of Energy. Funding for the University of Maryland was initially modest (40k/year) for the first two years. The remaining four years were funded at 201k/year, with a single $50k supplemental in 2015, and a no-cost extension that ran through March, 2018. The CSPM involved several institutions whose efforts are documented separately. At UMD, the CSPM supported two graduate students (Kanekar and Wilkie), two post-doctoral fellows (Landreman and TenBarge), and summer salary for the UMD PI (Dorland). The supplemental in 2015 provided additional salary for a sabbatical by Dorland in 2015/16. Landreman and TenBarge both transitioned to separately funded research staff positions at Maryland at the ends of their post-doctoral, CSPM-supported, positions.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2020

Overview of FY20 Q2 milestone completion: Actuator Disk Improvements and Hardening PowerPoint]

Milestone Description: Enhance Nalu-Wind's actuator disc model through hardening, documenting, stress-testing, verifying, and validating. Existing workflows will be improved by reducing the data output stream, and by making the analysis capabilities more modular and generally better. These model capabilities are needed by other A2e areas, namely Wake Dynamics, AWAKEN, and VV&UQ.

36 MATERIALS SCIENCE↗
DOE OSTI2019

In-situ small-scale mechanical testing of fast reactor mixed oxide pins: completion report

The present work represents a pioneering study in the application of advanced techniques to measure micro-mechanical properties of highly radioactive advanced nuclear fuels. First data of Young’s modulus and hardness of fast reactor MOX at burnup exceeding 150 GWd/tHM have been obtained. Despite the challenges encountered in the current work due to equipment malfunction, the experimental approach sought in this work has been proved successful in obtaining new data of high relevance for fuel performance on system with high Pu content and high radiotoxicity with extremely limited exposure to personnel. Further experiments will be conducted in the future based on the present approach, leveraging the experience gained in this project.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2020

Report on partially complete post-irradiation-examination of the INL samples

Ferritic-martensitic steels (NF616 and T91), and austenitic stainless steel 800H and its Grain Boundary Engineering (GBE)-treated version 800H-TMP (ThermoMechanical Processing) were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) and their microstructures and mechanical properties were characterized. Ferritic-martensitic steels were irradiated up to 8.16 dpa in the irradiation temperatures ranging from 241 °C to 447.5 °C. Selected 800H and 800H-TMP samples were also irradiated up to 9.12 dpa at 359°C to 431°C. Vickers hardness measurement, fractography, and microstructural characterization were performed on the selected samples in the LAMDA lab. Radiation-induced hardening of NF616 and T91 was observed in the hardness measurements which show ~37% to ~65% increases, depending on irradiation dose and irradiation temperature. Within the irradiation conditions studied in this work, samples with a higher dose had a higher hardness. All the tested alloy 800H and 800H-TMP in this work showed irradiation-hardening by ~96±7% to ~152±10%. Alloy 800HTMP tended to have slightly smaller irradiation-hardening than alloy 800H. The fractography of NF616 samples D2 (2.96 dpa at 291.5°C), D4 (5.91 dpa at 359°C), and D6 (8.16 dpa at 431°C) indicated loss of ductility with negligible necking for the sample D2, yet obvious ductile failure for samples D4 and D6. Fractography of alloy 800H samples N4 (7.27 dpa at 359°C), N5 (3.9 dpa at 451.5°C), and N6 (9.01 dpa at 431°C), and alloy 800H-TMP samples P4 (7.36 dpa at 359°C), P5 (3.95 dpa at 451.5°C), and P6 (9.12 dpa at 431°C) indicated that all samples failed in a ductile mode, with obvious necking. Dimples were observed where large Ti-containing particles were observed for the samples. TEM characterization was performed on alloy 800H (N4, N5, N6) and 800H-TMP (P4, P5 and P6). Accumulation of M23C6 precipitates at grain boundaries was observed in all samples, and the presence of Ti(C,N) precipitates at grain boundaries and in the matrix was observed in alloy 800H-TMP. M23C6 precipitates were found to have the cube-on-cube orientation relationship with the matrix. In addition, nanoscale Si-rich clusters were observed in the matrix of all samples. Atom probe tomography was conducted on the same samples, and their results are being analyzed to be integrated with the TEM results for a confident description of the clustering behavior. Due to the low irradiation temperature (up to 451.5°C), dislocation loops formed in all samples, with the density and the average size of dislocation loops in the order of 1022 – 1023 m-3 and 11.7 – 15.9 nm, respectively. The loop densities in alloy 800H were higher than that in alloy 800H-TMP under the same irradiation conditions. Further systematic data analyses, together with some complementary experiments, will be pursued for these samples to foster peer-reviewed journal article publications.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2020

Complete Round-Robin Hydrogen Gas Analysis Capability Comparison (Milestone 2.6)

The Department of Energy (DOE) is currently evaluating strategies for the extended dry storage of aluminum-clad spent nuclear fuel (ASNF). Part of this assessment concerns the extent of radiolytic molecular hydrogen (H2) generation from the aluminum cladding’s oxyhydroxide corrosion layers. Understanding this radiation-induced process and the factors effecting it (e.g., system conditions such as temperature and gaseous environment) are essential for the development of predictive computer models to support the Technical Considerations and Challenges for Extended (> 50 yrs) Dry Storage of ASNF program. To achieve this goal and ensure that the experimental data gathered by Task 2 (Oxyhydroxide Layer Radiolytic Gas Generation Resolution) research groups (Idaho National Laboratory and Savannah River National Laboratory) are consistent, a round-robin H2 analysis capability comparison was initiated. Here we present the results from said round-robin and conclude that despite differences in sample preparation, irradiation parameters, and analytical procedures, the measured data are sufficiently consistent between the two laboratories (= 15%).

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
DOE OSTI2020

Laboratory Directed Research and Development Program (FY 2019 Annual Summary of Completed Projects)

Oak Ridge National Laboratory (ORNL) is the US Department of Energy’s (DOE’s) largest multiprogram science, technology, and energy laboratory with distinctive capabilities in neutron science, computing, advanced materials, and nuclear science and technology. Using these capabilities, ORNL conducts basic and applied research and development (R&D) to support DOE’s overarching mission to “ensure America’s security and prosperity by addressing its energy, environmental and nuclear challenges through transformative science and technology solutions.” As a national resource, ORNL also applies its capabilities and skills to specific needs of other federal agencies and customers through the DOE Strategic Partnership Projects (SPP) program. Information about the laboratory and its programs is available at the ORNL website. The Laboratory Directed Research and Development (LDRD) program at ORNL operates under the authority of the DOE Order 413.2C, “Laboratory Directed Research and Development,” which establishes DOE’s requirements for the program while providing the laboratory director broad flexibility for program implementation. The LDRD program funds are obtained through a charge to all laboratory programs. ORNL reports on the program status to DOE each year.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2021

Completion of Irradiation of Sensors in ATRC Milestone

This set of PowerPoint slides demonstrates how milestone "M2CT-21IN0702023: Perform test of neutron flux sensors in the Advanced Test Reactor Critical Facility". It supports an entry in PICS claiming achievement of the milestone. These slides provide a good summary of the purpose and impact of the milestone for our DOE Headquarters colleagues.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2021

Classified Library Completes Large Digitization Project of Patent Collection

Many of us regularly enjoy the online resources provided by the National Security Research Center (NSRC), which is the Lab’s classified library. However, you may not be aware of all the work that goes on behind the scenes to digitize articles, reports, photographs, and correspondence. This process not only preserves documents, many of which date back to the Manhattan Project era, but also ensures they are searchable and accessible for today’s national security work. You also may not be aware that a vast majority of the Laboratory’s information holdings have not yet been digitized. And by vast majority, I mean perhaps 90% of the millions of holdings in the NSRC is only available in hard copy.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗
DOE OSTI2021

Completion of Milestone for Receiving Reinstrumentation Equipment from IFE

This set of powerpoint slides demonstrates how milestone "M2CT-21IN0702026: Receive prototype drilling and defueling modules for the re-instrumentation facility procured from the Institute For Energy (Halden, Norway) at the Idaho National Laboratory" was met. It supports an entry in PICS claiming achievement of the milestone. These slides provide a good summary of the purpose and impact of the milestone for our DOE Headquarters colleagues.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2013

Completed UIC Permit Document (SECARB Work Product 3.2.4.b)

The Southeast Regional Carbon Sequestration Partnership’s (SECARB’s) Anthropogenic Test is a demonstration of the deployment of CO 2 capture, transport, geologic storage and monitoring technologies. The capture component of the test takes place at the James M. Barry Electric Generating Plant in Bucks, Alabama. The capture facility utilizes post-combustion amine capture technology licensed from Mitsubishi Heavy Industries America to process flue gas from a coal-fired power unit at Plant Barry. The amount of CO 2 captured using this process is equivalent to the emissions produced when generating 25 megawatts (MW) of electricity. CO 2 captured at the plant is transported by pipeline for underground storage in a saline geologic formation within the Citronelle Dome. This project is one of the first and the largest fully-integrated commercial prototype coal-fired carbon capture and storage projects in the USA.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2013

Completed Drilling Permit (SECARB Phase III Work Product 3.2.6.a)

The Southeast Regional Carbon Sequestration Partnership’s (SECARB’s) Anthropogenic Test is a demonstration of the deployment of CO 2 capture, transport, geologic storage, and monitoring technologies. The capture component of the test takes place at the James M. Barry Electric Generating Plant in Bucks, Alabama. The capture facility utilizes post-combustion amine capture technology licensed from Mitsubishi Heavy Industries America to process flue gas from a coal-fired power unit at Plant Barry. The amount of CO 2 captured using this process is equivalent to the emissions produced when generating 25 megawatts (MW) of electricity. CO 2 captured at the plant is transported by pipeline for underground storage in a saline geologic formation within the Citronelle Dome. This project is one of the first and the largest fully-integrated commercial prototype coal-fired carbon capture and storage projects in the USA.

01 COAL, LIGNITE, AND PEAT↗
DOE OSTI2013

Completed and Interpreted Baseline Seismic Survey Report (SECARB Phase III Work Product 4.2.2.b)

Advanced Resources presents the results of the seismic survey performed at the SECARB Citronelle project in Alabama. The CO 2 monitoring effort for the Anthropogenic Test includes two wellbore seismic methods, specifically time-lapse crosswell seismic and vertical seismic profiles (VSP). Due to the unique challenges presented by this test (injection depth of 9,500+ ft. into thin, stacked reservoir sands and limited injection volumes) surface seismic was eliminated as a Monitoring, Verification, and Accounting (MVA) tool. However, the newly drilled project wells provided ample casing diameters (prior to running tubing) to accommodate wellbore seismic receivers (wireline and tubing deployed) and a crosswell source. Baseline surveys were conducted in 2012 prior to the onset of CO 2 injection operations. Reports document the results from the baseline vertical seismic profile (VSP) and crosswell seismic surveys performed by SR2020 and Schlumberger Carbon Services, respectively.

54 ENVIRONMENTAL SCIENCES↗