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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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DOE OSTI2016

Digital Image Correlation for Performance Monitoring.

Evaluating the health of a mechanism requires more than just a binary evaluation of whether an operation was completed. It requires analyzing more comprehensive, full-field data. Health monitoring is a process of nondestructively identifying characteristics that indicate the fitness of an engineered component. In order to monitor unit health in a production setting, an automated test system must be created to capture the motion of mechanism parts in a real-time and non-intrusive manner. One way to accomplish this is by using high-speed video (HSV) and Digital Image Correlation (DIC). In this approach, individual frames of the video are analyzed to track the motion of mechanism components. The derived performance metrics allow for state-of-health monitoring and improved fidelity of mechanism modeling. The results are in-situ state-of-health identification and performance prediction. This paper introduces basic concepts of this test method, and discusses two main themes: the use of laser marking to add fiducial patterns to mechanism components, and new software developed to track objects with complex shapes, even as they move behind obstructions. Finally, the implementation of these tests into an automated tester is discussed.

47 OTHER INSTRUMENTATION↗

DOE OSTI2016

Emerging Technologies and Techniques for Wide Area Radiological Survey and Remediation

Technologies to survey and decontaminate wide-area contamination and process the subsequent radioactive waste have been developed and implemented following the Chernobyl nuclear power plant release and the breach of a radiological source resulting in contamination in Goiania, Brazil. These civilian examples of radioactive material releases provided some of the first examples of urban radiological remediation. Many emerging technologies have recently been developed and demonstrated in Japan following the release of radioactive cesium isotopes (Cs-134 and Cs-137) from the Fukushima Dai-ichi nuclear power plant in 2011. Information on technologies reported by several Japanese government agencies, such as the Japan Atomic Energy Agency (JAEA), the Ministry of the Environment (MOE) and the National Institute for Environmental Science (NIES), together with academic institutions and industry are summarized and compared to recently developed, deployed and available technologies in the United States. The technologies and techniques presented in this report may be deployed in response to a wide area contamination event in the United States. In some cases, additional research and testing is needed to adequately validate the technology effectiveness over wide areas. Survey techniques can be deployed on the ground or from the air, allowing a range of coverage rates and sensitivities. Survey technologies also include those useful in measuring decontamination progress and mapping contamination. Decontamination technologies and techniques range from non-destructive (e.g., high pressure washing) and minimally destructive (plowing), to fully destructive (surface removal or demolition). Waste minimization techniques can greatly impact the long-term environmental consequences and cost following remediation efforts. Recommendations on technical improvements to address technology gaps are presented together with observations on remediation in Japan.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2017

Mini-Split Heat Pump Evaluation and Zero Energy Ready Home Support

This project was created from a partnership between the U.S. Department of Energy’s (DOE’s) Building America research team IBACOS, Inc. and Imagine Homes, a production homebuilder of high-performance homes in San Antonio, Texas—a hot-humid climate. The primary purpose was to evaluate the performance of a multihead mini-split heat pump (MSHP) space-conditioning system, which consists of ducted and ductless indoor units, in maintaining uniform comfort in an occupied test house. The research team evaluated the MSHP space-conditioning strategy for its effectiveness in achieving uniform temperature and relative humidity (RH) levels throughout the test house and for overall constructability and cost. This evaluation was based on data that were collected from short-term tests and monitoring during 1 year of occupancy, as well as from builder and occupant feedback. Design considerations for integrating an MSHP system into the builder’s full range of production home designs were also explored, with a focus on minimizing the cost and complexity of the system design while meeting the thermal loads of the house and providing occupant comfort according to ANSI/ASHRAE Standard 55-2010 (ASHRAE 2010a).

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

DOE OSTI2015

Tests of a High Temperature Sample Conditioner for the Waste Treatment Plant LV-S2, LV-S3, HV-S3A and HV-S3B Exhaust Systems

Tests were performed to evaluate a sample conditioning unit for stack monitoring at Hanford Tank Waste Treatment and Immobilization Plant (WTP) exhaust stacks with elevated air temperatures. The LV-S2, LV-S3, HV-S3A and HV-S3B exhaust stacks are expected to have elevated air temperature and dew point. At these emission points, exhaust temperatures are too high to deliver the air sample directly to the required stack monitoring equipment. As a result, a sample conditioning system is considered to cool and dry the air prior to its delivery to the stack monitoring system. The method proposed for the sample conditioning is a dilution system that will introduce cooler, dry air to the air sample stream. This method of sample conditioning is meant to reduce the sample temperature while avoiding condensation of moisture in the sample stream. An additional constraint is that the ANSI/HPS N13.1-1999 standard states that at least 50% of the 10 μm aerodynamic diameter (AD) particles present in the stack free stream must be delivered to the sample collector. In other words, depositional loss of particles should be limited to 50% in the sampling, transport, and conditioning systems. Based on estimates of particle penetration through the LV-S3 sampling system, the diluter should perform with about 80% penetration or better to ensure that the total sampling system passes the 50% or greater penetration criterion.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2018

Nevada National Security Site Integrated Groundwater Sampling Plan, Revision 1

The purpose is to provide a comprehensive, integrated approach for collecting and analyzing groundwater samples to meet the needs and objectives of the DOE/EM Nevada Program’s UGTA Activity. Implementation of this Plan will provide high-quality data required by the UGTA Activity for ensuring public protection in an efficient and cost-effective manner. The Plan is designed to ensure compliance with the UGTA Quality Assurance Plan (QAP) (NNSA/NFO, 2015); Federal Facility Agreement and Consent Order (FFACO) (1996, as amended); and DOE Order 458.1, Radiation Protection of the Public and the Environment (DOE, 2013). The Plan’s scope comprises sample collection and analysis requirements relevant to assessing both the extent of groundwater contamination from underground nuclear testing and impact of testing on water quality in downgradient communities. This Plan identifies locations to be sampled by CAU and location type, sampling frequencies, sample collection methodologies, and the constituents to be analyzed. In addition, the Plan defines data collection criteria such as well purging, detection levels, and accuracy requirements/recommendations; identifies reporting and data management requirements; and provides a process to ensure coordination between NNSS groundwater sampling programs for sampling analytes of interest to UGTA. Information used in the Plan development—including the rationale for selection of wells, sampling frequency, and the analytical suite—is discussed under separate cover (N-I, 2014) and is not reproduced herein. This Plan does not address compliance for those wells involved in a permitted activity. Sampling and analysis requirements associated with these wells are described in their respective permits and are discussed in NNSS environmental reports (see Section 5.2). In addition, sampling for UGTA CAUs that are in the Closure Report (CR) stage are not included in this Plan. Sampling requirements for these CAUs are described in the CR. Frenchman Flat is currently the only UGTA CAU in the CR stage. Sampling requirements for this CAU are described in Underground Test Area (UGTA) Closure Report for Corrective Action Unit 98: Frenchman Flat Nevada National Security Site, Nevada (NNSA/NFO, 2016).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2014

NMSBA High Frequency Modal Analysis of a Solid Metal Cylinder

This memo documents the results and methodology of the high-frequency modal test performed on a solid metal cylinder, provided by Vibrant Corporation, in September 2014 at Sandia National Laboratories. The purpose of this test was to measure mode shapes of the unit (torsion, axial, and bending) as high in frequency as achievable with a Polytec PSV-400 scanning laser Doppler vibrometer.

42 ENGINEERING↗

DOE OSTI2019

Integrated Oxygen Production and CO 2 Separation through Chemical Looping Combustion with Oxygen Uncoupling (Final Report)

The project "Integrated Oxygen Production and CO 2 Separation through Chemical Looping Combustion with Oxygen Uncoupling" focused on advancing fluidized bed chemical looping combustion technology to semi-pilot scale. An important aspect of technology scale-up is production of well-performing oxygen carrier materials economically and at a scale sufficient for industrial-scale systems. Under this program, a new technique for oxygen carrier production was developed and a prototype system capable of producing up to 150 lb per batch of oxygen carrier was constructed. Chemical looping combustion testing was performed in a large process development unit designed for operation at more than 200 kW using coal as fuel. Complementary evaluation of carbon conversion pathways was conducted and quantitative analysis of the fate of carbon in a CLOU-based chemical looping system was performed. As an aid for design, optimization, troubleshooting and scale-up, robust CFD models for fluidized bed chemical looping combustion systems were developed.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2015

Baseline Monitoring of CO 2 Fluids

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2016

SECARB Report on Post-Injection Surface and Near-Surface Monitoring

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2015

Southeast Carbon Sequestration Partnership (SECARB) Phase III Anthropogenic Test at Citronelle Field, Mobile Co., AL Surface and Shallow Subsurface Monitoring

The Southeast Carbon Sequestration Partnership Phase III Anthropogenic Test at Citronelle Field is one of the United States’ largest demonstrations of CO 2 capture, transportation, injection, storage and monitoring using CO 2 derived from a coal-fired electric generating unit. This report summarizes the background and initial injection phase groundwater and soil flux monitoring results. The purpose of the groundwater monitoring program, as prescribed in the Underground Injection Control (UIC) permits is to assure that the project’s activities do not harm Underground Sources of Drinking Water (USDWs). In particular, the objective of the program is to monitor for the release of injected CO2 into groundwater aquifers at the project site. Three shallow USDW monitoring wells were installed as part of the groundwater monitoring program. In addition, a water supply well located near the project’s deep characterization well was utilized for monitoring. Seventeen metals, general chemistry and field parameters (e.g. pH, specific conductance, turbidity) were sampled three times prior to injection and quarterly during the injection period to date. Changes in groundwater geochemistry potentially attributable to a release of carbon dioxide into the USDW from the injection activities are decreasing pH and increasing TIC. The change in pH may also accompany the mobilization of certain metals within the groundwater, but the changes are likely site-specific, based on the natural aquifer mineralogy (Wilkin and Diguilio, 2010). At this time, no downward trends for pH and increasing trends for TIC have been statistically determined in the monitor wells. Valid detections exceeding both the UIC discharge limit and the range of background concentrations observed as of the N=11 event include: Exceedance of the UIC permit discharge limit of manganese at D-9-7 MW-2S and D-9-9 MW-1, and exceedance of the UIC permit discharge limit of iron at D-9-9 MW-1. In addition, a statistically significant increase of barium and manganese has been observed at D-9-9 MW-1. However, Additional lines of evidence (namely, expected shifts in TIC or pH, per the research cited above) to interpret the cause (e.g., potential carbon dioxide influence) of the statistically determined exceedances and/or increases are absent at this time. Quarterly groundwater sampling and analysis will continue throughout the project. The UIC permit requires that soil CO 2 flux shall be monitored at the land surface at the injection site and at nearby locations. Twelve locations were chosen for surveys including a mix of near wellbore and offset locations. To date, 24 surveys have taken place with 12 occurring prior to the onset of injection operations in August 2012. Soil CO 2 flux appears to positively covary with soil temperature. A notably high soil CO 2 flux value (21 µmol/m 2 /sec) was observed from the D-9-9 #2 chamber location during sampling event #24 (9/24/2014). As a result of this finding, the frequency of soil CO 2 flux monitoring events will be increased to twice-monthly until this anomaly can be confirmed or determined to be an outlier. Soil CO 2 flux monitoring will continue for the duration of the project.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2025

Nuclear Materials Packaging, Transportation, and Systems Analysis Group Software Quality Assurance Plan: ANSYS Mechanical Finite Element Analysis Software Version 2023R1

ANSYS Inc. develops and markets engineering simulation software and services used in the aerospace, automotive, manufacturing, electronics, biomedical, energy, defense, and many other industries. ANSYS is dedicated to engineering simulation and is the world’s leading software provider. ANSYS was founded in 1970 and is headquartered in Canonsburg, Pennsylvania. ANSYS provides an engineering analysis tool combining structural, thermal, computational fluid dynamics, acoustic, and electromagnetic simulation capabilities. ANSYS has two main programs, which use the same solvers: (1) Mechanical APDL (ANSYS Design Parametric Language), a Fortran-based coding platform, and (2) ANSYS Workbench, which uses a graphical user interface to aid in finite element analysis implementation. This plan covers both APDL and Workbench. The ANSYS computer program is a large-scale, multipurpose finite element program that can be used to solve several classes of engineering analyses. The analysis capabilities of ANSYS include the ability to solve static and dynamic structural analyses, steady-state and transient heat transfer problems, mode-frequency and buckling eigenvalue problems, static or time-varying magnetic analyses, and various types of field and coupled-field applications. The program contains many special features that allow nonlinearities or secondary effects such as plasticity, large strain, hyperelasticity, creep, swelling, large deflections, contact, stress stiffening, temperature dependency, material anisotropy, and radiation to be included in the solution. As ANSYS has been developed, other special capabilities such as substructuring, submodeling, random vibration, kinetostatics, kinetodynamics, free convection fluid analysis, acoustics, magnetics, piezoelectrics, coupled-field analysis, and design optimization have been added to the program. These capabilities contribute further to making ANSYS a multipurpose analysis tool for varied engineering disciplines. The ANSYS program has been in commercial use for over 50 years and has been used extensively in the aerospace, automotive, construction, electronic, energy services, manufacturing, nuclear, plastics, oil, and steel industries. Additionally, many consulting firms and hundreds of universities have used ANSYS for analysis, research, and educational purposes. ANSYS is recognized worldwide as one of the most widely used and capable programs of its type. Ansys design analysis software is the first created within a quality system with ISO 9001 certification, the internationally accepted quality standard. Product development, testing, maintenance and support processes also meet the United States Nuclear Regulatory Commission's quality requirements, as they have for nearly four decades. The Quality Assurance Service Agreement is suitable for the customers working in the nuclear industry who need to meet specific federal regulations including 10CRF50 Appendix B and provisions of 10CFR21. ANSYS has retained its original International Organization for Standardization (ISO) 9001 accreditation certificate since1995-05-04, It’s current certificate is valid until 2027-05-29.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2025

Tests of a High Temperature Sample Conditioner for the Waste Treatment Plant LV-S2, LV S3, HV S3A and HV-S3B Exhaust Systems

Tests were performed to evaluate a sample conditioning unit for stack monitoring at Hanford Tank Waste Treatment and Immobilization Plant (WTP) exhaust stacks with elevated air temperatures. The LV-S2, LV-S3, HV-S3A and HV-S3B exhaust stacks are expected to have elevated air temperature and dew point. At these emission points, exhaust temperatures are too high to deliver the air sample directly to the required stack monitoring equipment. As a result, a sample conditioning system is considered to cool and dry the air prior to its delivery to the stack monitoring system. The method proposed for the sample conditioning is a dilution system that will introduce cooler, dry air to the air sample stream. This method of sample conditioning is meant to reduce the sample temperature while avoiding condensation of moisture in the sample stream. An additional constraint is that the ANSI/HPS N13.1-1999 standard states that at least 50% of the 10 µm aerodynamic diameter (AD) particles present in the stack free stream must be delivered to the sample collector. In other words, depositional loss of particles should be limited to 50% in the sampling, transport, and conditioning systems. Based on estimates of particle penetration through the LV-S3 sampling system, the diluter should perform with about 80% penetration or better to ensure that the total sampling system passes the 50% or greater penetration criterion.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2015

2015 Stewardship Science Academic Programs Annual

The Stockpile Stewardship Academic Programs (SSAP) are essential to maintaining a pipeline of professionals to support the technical capabilities that reside at the National Nuclear Security Administration (NNSA) national laboratories, sites, and plants. Since 1992, the United States has observed the moratorium on nuclear testing while significantly decreasing the nuclear arsenal. To accomplish this without nuclear testing, NNSA and its laboratories developed a science-based Stockpile Stewardship Program to maintain and enhance the experimental and computational tools required to ensure the continued safety, security, and reliability of the stockpile. NNSA launched its academic program portfolio more than a decade ago to engage students skilled in specific technical areas of relevance to stockpile stewardship. The success of this program is reflected by the large number of SSAP students choosing to begin their careers at NNSA national laboratories.

Stone, Terri↗

DOE OSTI2016

DESIGN CHARACTERISTICS OF THE IDAHO NATIONAL LABORATORY HIGH-[TEMPERATURE GAS-COOLED TEST REACTOR

A point design for a graphite-moderated, high-temperature, gas-cooled test reactor (HTG TR) has been developed by Idaho National Laboratory (INL) as part of a United States (U.S.) Department of Energy (DOE) initiative to explore and potentially expand the existing U.S. test reactor capabilities. This paper provides a summary of the design and its main attributes. The 200 MW HTG TR is a thermal-neutron spectrum reactor composed of hexagonal prismatic fuel and graphite reflector blocks. Twelve fuel columns (96 fuel blocks total and 6.34 m active core height) are arranged in two hexagonal rings to form a relatively compact, high-power density, annular core sandwiched between inner, outer, top, and bottom graphite reflectors. The HTG-TR is designed to operate at 7 MPa with a coolant inlet/outlet temperature of 325°C/650°C, and utilizes TRISO particle fuel from the DOE AGR Program with 425 ?m uranium oxycarbide (UCO) kernels and an enrichment of 15.5 wt% 235U. The primary mission of the HTG TR is material irradiation and therefore the core has been specifically designed and optimized to provide the highest possible thermal and fast neutron fluxes. The highest thermal neutron flux (3.90E+14 n/cm2s) occurs in the outer reflector, and the maximum fast flux levels (1.17E+14 n/cm2s) are produced in the central reflector column where most of the graphite has been removed. Due to high core temperatures under accident conditions, all the irradiation test facilities have been located in the inner and outer reflectors where fast flux levels decline. The core features a large number of irradiation positions with large test volumes and long test lengths, ideal for thermal neutron irradiation of large test articles. The total available test volume is more than 1100 liters. Up to four test loop facilities can be accommodated with pressure tube boundaries to isolate test articles and test fluids (e.g., liquid metal, liquid salt, light water) from the helium primary coolant system.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2026

Combined radiation environment modeling using the Scorpius linear induction accelerator

Explore the source record for details and available documents.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2019

Hydrodynamic and Structural Response Modeling of a Prototype Floating Membrane Reservoir System for Pumped Storage Hydropower

Hydrodynamic, computational fluid dynamics, and finite-element modeling were performed for a novel floating membrane reservoir system design for closed-loop pumped storage hydropower application. The conceptual design, which is now protected under an invention disclosure with a patent pending, offers a potential low-cost, low-impact solution to address the high costs, long investment return periods, and environmental disruptions encountered with traditional pumped storage development while offering modularity to enable replication at many locations. Prior to physical tests on a prototype, this paper documents the response analysis and modeling completed to simulate hydraulic and structural performance under different reservoir deployment and alignment arrangements, evaluate system stability, and refine the conceptual design. The results indicate that the excitation frequency from vortex shedding is at least an order of magnitude lower than the water sloshing frequencies in the reservoir, the structural natural frequency of the entire reservoir, and the vibrational frequencies of the side membranes, although excitation frequencies from other sources could cause mechanical resonance under certain conditions. To control destabilizing effects and prevent rocking motion and vibration, the authors conclude that the design could be improved by including a support structure around the floating reservoir, which could also provide floating-membrane containment, improve safety, and facilitate vertical reservoir movement. These conclusions, based on hydrodynamic and structural response modeling, help define specifications for upcoming full-scale prototype construction, deployment, and testing. This study demonstrates standard modeling technique application to an innovative design for which similar applications have not been previously evaluated. As a result, the refined design is capable of improving the scalability and feasibility of pumped storage hydropower in the United States and will be considered for commercialization following prototype testing.

13 HYDRO ENERGY↗

DOE OSTI2019

Low-cost Oxygen (LCO) for Small-scale Modular Gasification Systems

Development of a sorbent-based vacuum pressure swing adsorption oxygen production technology was undertaken. Newly developed perovskite ceramic sorbent materials have a higher O 2 adsorption capacity, lower operating temperatures (550-600 °C vs 800-850 °C), and an order of magnitude faster desorption rate than those used in earlier development efforts. These performance advancements lead to substantial savings in capital investment and operational costs. Cost of producing oxygen using the new sorbents can be considerably lower than a cryogenic air separation unit. Development of these new sorbents and design and fabrication of a pilot demonstration unit (PDU) encompassed lab-scale work, bench-scale testing and development, demonstration-scale sorbent manufacturing, procurement of plant components, and final assembly and testing of the PDU. The goal of the project was to develop an advanced oxygen production technology based on improved perovskite ceramic sorbents that results in significantly lower oxygen cost compared to commercial state of the art technologies. The pilot demonstration unit was constructed and operated, but the performance of the scaled-up sorbent and the PDU was hindered by the mechanical problems with the system. When the problems are accounted for, the results show that the PDU would be able to produce 95% oxygen at a rate exceeding one ton per day. The same mechanical problems also mean that the PDU system was not fully optimized, which would increase the productivity as well.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2026

GPHS-RTG F5R Electrically Heated Thermal Vacuum Testing

Idaho National Laboratory (INL) has been tasked with the evaluation and refurbishment of the General Purpose Heat Source (GPHS) Radioisotope Thermoelectric Generator (RTG) Flight Unit 5 (GPHS-RTG F5R or F5R) that was defueled in 2005. This paper describes the testing of F5R in the thermal vacuum chamber and evaluation of the data demonstrating the generator meets updated Cassini-Huygens requirements. The generator produced 260 We of power at the specified 4100 Wth heat source inventory. This power exceeded the power requirement for 250 We , confirming system integrity and demonstrating that the generator is capable of potential NASA missions.

30 - DIRECT ENERGY CONVERSION↗