Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “LINER”

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 1,639 records · Page 91

Potential Improvements for the One-Dimensional Imager of Neutrons at the Sandia Z Facility

Understanding the neutron source shape is critical for improving Magnetized Liner Inertial Fusion (MagLIF) implosions at the Sandia Z machine. Neutron source-shape measurements for MagLIF are, however, challenging due to the yields, extended axial source regions, x-ray backgrounds and physical shock waves produced by MagLIF sources. Initial tests of a slit neutron imager for 1- dimensional neutron imaging along the axial dimension of MagLIF implosions have shown that a rolled-slit aperture and CR-39 plastic detector can image the neutron production along the axial dimension. In this whitepaper, we suggest straightforward improvements to the neutron imager design that will allow significantly improved signal-to-noise performance.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Examination of Shipping Package 9975-04194

In December 2017, K-Area personnel attempted to open package 9975-04194 to remove its contents. The upper fiberboard assembly could not be initially removed due to an interference fit that had developed against the lead shield. Corrosion of the shield created two specific conditions that caused this interference. First, there was widespread heavy blisters over the shield surface. Corrosion of the lead under the surface (associated with porosity in the as-cast shield which is open to the surface) appears to have caused the blisters to form. Second, corrosion also formed in a gap between the lead shield and the internal stainless steel liner, pushing the top edge of the shield outward into the upper fiberboard assembly. In both cases, portions of the shield are pushed outward since the corrosion product occupies a greater volume than the metallic lead it replaced.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

(U) Pre-shot Report: Complex Loading of CeO 2 Powder

A cylindrically converging shock compaction experiment is designed utilizing the Precision High Energy-density Liner Implosion eXperiment (PHELIX) platform to dynamically load CeO 2 powder. Parametric analyses investigating the effect of PHELIX cassette geometry, PHELIX total capacitor charge, and powder compaction model on the predicted shocked density profile of the CeO 2 powder are performed using the LANL codes FLAG and RAVEN. One PHELIX cassette geometry is designed to be used in two compaction experiments using PHELIX capacitor charges of 85 and 90 kV. Predictions of the shocked density profile in the CeO 2 powder are presented for each experimental configuration using both the Ramp and P-α compaction models. The two compaction models predict shocked density profiles in the CeO 2 powder that are significantly different and should be distinguishable using proton radiography as a diagnostic.

36 MATERIALS SCIENCE↗

As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility

The performance assessment (PA) for the Idaho National Laboratory (INL) Remote Handled Low Level Waste (RH LLW) disposal facility (U.S. Department of Energy [DOE]-ID 2012) is required to demonstrate that the facility design will meet the performance objectives established for long term protection of the public and the environment following closure of the facility as outlined in DOE Order 435.1, “Radioactive Waste Management.” Protectiveness of the facility in terms of the groundwater pathway is a function of the design features that control the hydrologic and geochemical conditions within and below the vault system. The facility design includes features to promote drainage of infiltrating water to limit accumulation of moisture next to the reinforced concrete disposal vaults and containerized waste. The PA groundwater pathway model accounts for a cement impacted geochemical environment within and below the vault system to inhibit corrosion of stainless steel waste containers (i.e., waste liners), steel reinforcement in the concrete vault, and the effects on release and migration of non anionic radionuclides. Upon closure of the facility, an engineered barrier (i.e., cover) will be placed over the facility to reduce infiltration through the waste zone, retarding the release and migration rate of radionuclides beneath the facility. Crediting the long-term performance of the vault system requires characterization of the hydraulic and concrete performance over time. Verification of the vault performance requires monitoring for radiologic releases from the facility. The purpose of this document is to provide the description of the characterization and monitoring system installed at the facility to accomplish these two objectives.

99 GENERAL AND MISCELLANEOUS↗

Updated Draft ASME Boiler and Pressure Vessel Code Case for Use of Alloy 617 for Construction of Nuclear Components for Section III Division 5

Early in the United States’ very high temperature reactor program, several candidate nickel alloys were considered for use in construction of the intermediate heat exchanger. Based primarily on technical maturity, a downselection was made to focus on Alloy 617. After this downselection, the primary goal of the research and development program was to develop sufficient information on the high temperature properties of the material to qualify it for construction of high temperature nuclear components in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code. Alloy 617 is a solid solution strengthened material with nominal Ni Cr Co Mo composition, originally developed for aerospace applications such as burner can liners for turbine engines by Huntington Alloys. (Huntington Alloys is now Special Metals Division of Precision Castparts, Inc.) The ASME BPV Code allows use of Alloy 617 for construction of non nuclear pressure vessels, and Alloy 617 is used in fossil fired power plants. Section III, Division 1, Subsection NB of the ASME BPV Code was developed for construction of nuclear components in light water reactors and allows use of ferritic materials up to 700°F and austenitic alloys up to 800°F. Subsection NH of Section III Division 1 was written to allow higher temperature construction with a primary focus on sodium cooled reactors. Recently, a new Division 5 of Section III was published specifically for high temperature reactors (regardless of the primary working fluid) and incorporates both Subsections NB and NH. There are only five alloys currently allowed for use in high temperature nuclear components: 2.25Cr 1 Mo and V modified 9Cr 1Mo steels, Types 304 and 316 stainless steels, and the high nickel austenitic Alloy 800H. This very sparse set of allowed materials is in contrast with the collection of more than 150 materials that are allowed for use in non nuclear pressure vessel construction. A draft Code Case to add Alloy 617 to the list of qualified alloys for use in high temperature nuclear design was submitted to ASME in the early 1990s, but it was withdrawn prior to formal Code action.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

2018 Bryan Mound Baseline Casing Analysis

This report analyzes data from multi-arm caliper (MAC) surveys taken at the Bryan Mound Strategic Petroleum Reserve site to determine baseline statistics for the original innermost cemented casing or the subsequent installed liner. Along with analyzing the internal diameters from the MAC surveys, this analysis looks to approximate casing weight, an important metric for determining the strength of well sections. Casing weight is calculated for each section, survey, and well. Results from the analysis show most wells reflect the dimensions in the original as-built drawings. There are, however, a few exceptions. Some well sections have calculated wall thicknesses outside API tolerance. In addition, some well section depths differ from the as-built drawings. All results are discussed on a well-by-well basis. Where applicable, information from this report should be used to update as-built drawings and aid in creating more accurate well models for future studies.

02 PETROLEUM↗

NDT System for Metal Components in Concrete Structures (Final Report)

Steel reinforcements embedded within concrete can corrode and crack, leading to weakening of the structures, and existing NDT (non-destructive testing) techniques do not provide the full picture. Condition assessment is critical in evaluating these structures in order to ensure safe, long-term operation of the nuclear power plants. Improved NDT techniques are needed as the nation’s generating stations age and require action based on increasingly critical inspection data. The power industry uses eddy current test (ECT) during in-service inspections to detect and monitor defects such as cracks and corrosion in metals, particularly metal pipes. However, the detection of defects in the reinforcing steel embedded in concrete is far more challenging for numerous reasons. Primary among them is the concrete layer’s thickness, which prevents the ability to have a close proximity between sensor and metallic sample. One solution to this problem is to create a higher sensitivity technique which can inspect at depth, with good spatial resolution and excellent directional sensitivity, to isolate the metal buried deep in the concrete and characterize defects in the metal. The goal of the phase II research program was to study and develop a new reinforced concrete NDT technology based on anisotropic magnetoresistive (AMR) sensors designed specifically for ECT of steel reinforcements in concrete. The first technical objective was to demonstrate the capability of inspecting steel reinforcement structures, including metal rebar and tensioning cable at or below 6” of depth embedded in concrete. Another objective was to be able to confidently identify multiple layers of reinforcements at varying depths. In addition, the technique needed to be able to provide condition assessment of the metal, providing data on the structure and positioning of the steel members, material loss, and detection of the presence of breaks. An important part of the research and development was aimed at achieving superior performance compared to existing technology. The ability to detect corrosion breaks in unbonded multi-wire and multi-strand tendons was another important objective. The final objective that led to a successful program was to build a complete prototype portable scanning system capable of demonstrating the probe performance in the field. All of these objectives were met, which provided data for the system development work going forward. RMD worked with the engineering firm Simpson Gumpertz & Heger to develop a detailed problem definition for concrete structures and the necessary sensor specifications. In addition, we developed finite element simulation models for the eddy current based NDT system through the analysis of the electromagnetic (EM) properties of sample materials and the orientation of the transmitter, sensor array (receivers), metal, and intervening materials like concrete and air. Based on the modeling and specifications, we designed and fabricated prototype sensor modules. We then acquired and fabricated test samples to characterize and optimize the sensors. Finally, we built a complete prototype for testing on actual concrete structures. This new NDT technology has high promise for greatly improving capabilities in the inspection of steel reinforcements within concrete structures, such as rebar, liners, anchors, and prestressing cables. This method could be valuable in the maintenance of nuclear power plants, and many other structures critical to our nation’s infrastructure.

42 ENGINEERING↗

Acoustic Channel Link Models for Digital Communication Protocols

Integration of advanced communication technologies into nuclear facility operation has the potential for enhancing safety and accident -resiliency of the existing fleet of aging light water reactors, as well those of future advanced reactors. Conventional wired and wireless communication systems face implementation challenges at nuclear facilities due to the presence of thick reinforced concrete walls with steel liners throughout much of nuclear facility, especially the containment building. In addition, concerns related to security gaps in conventional communication networks have to be addressed when developing communication systems for nuclear facilities. To address communication technology gaps for nuclear energy, we are currently developing the acoustic communication (AC) hardware and network protocols for efficient and secure transfer of data, and will provide a preliminary experimental demonstration of the AC system prototype in a representative environment.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

An Evaluation of Bang-Time Measurements from a Multichannel, Triaxial, nTOF Diagnostic for MagLIF Experiments at the Z facility

Neutron bang times for a series of MagLIF (Magnetic Liner Inertial Fusion) experiments with D 2 -filled targets have been measured at the Z facility. The emitted neutrons were detected as current-mode pulses in a multichannel, neutron time-of-flight (nTOF) diagnostic with conventional, scintillator-photomultiplier-tube (PMT) detectors. In these experiments, the detectors were fielded at known, fixed distances L (690-2510 cm) from the target, and on three, non-coplanar (but convergent) lines-of-sight (LOS). The primary goal of this diagnostic was to estimate a fiducial time (bang time) relative to an externally generated time-base for synchronizing all the diagnostics in an experiment. Recorded arrival times (A7) of the pulses were characterized experimentally by three numerical methods: a first-moment estimate (centroid) and two nodal measures — Savitzky-Golay (SG) smoothing and a single point peak estimate of the raw data. These times were corrected for internal detector time delays (transit and impulse-response function) — an adjustment that linked the recorded ATs to the corresponding arrival of uncollided neutrons at each detector. The bang time was then estimated by linearly regressing the arrival times against the associated distances to the source; t bang (on the system timescale) was taken as the temporal intercept of the regression equation at distance L = 0. This article reports the analysis for a representative shot #2584 for which (a) the recorded ATs — even without detector corrections — agreed by method in each channel to within 1-2 ns; (b) internal corrections were each ~3 — 5 ns; and (c) a 95% uncertainty (confidence) interval for t bang in this shot was estimated at ±3 ns with 4 degrees of freedom. A secondary goal for this diagnostic was to check that the bang time measurements corresponded to neutrons emitted by the D(d,n) 3 He reaction in a thermalized DD plasma. According to the theoretical studies by Brysk, such neutrons should be emitted with an isotropic Gaussian distribution of mean kinetic energy $ \overline{E}$ of 2.449 MeV; this energy translates to a mean neutron speed $ \overline{u}$ of 2.160 cm/ns [D. H. Munro, Nuclear Fusion, 56(3) 036001 (2016)]. In the MagLIF series of shots there was no evidence of spatial asymmetry in the time-distance regressions, and it was possible to extract the mean neutron speed from the slope of these fits. In shot 2584 $ \overline{u}$ was estimated at 2.152 cm/ns ± 0.010 cm/ns [95 % confidence, 4 dof] and the mean kinetic energy $ \overline{E}$ (with relativistic corrections) was 2.431 MeV ± 0.022 MeV [95 % confidence, 4 dof] — results supporting the assumption that D-D neutrons were, in fact, measured.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Beam-induced power in HEX SCW

A superconducting wiggler (SCW) is planned to be installed in NSLS-II for HEX beamline. Interaction of the electron beam with the resistive-wall impedance of the low-gap SCW liner and with the geometric impedance of the transition sections results in excitation of electromagnetic fields, dissipation of which contributes heat load in the cold volume. The beam-induced power caused by the beam-impedance interaction is estimated using analytical formulae and computer simulations.

36 MATERIALS SCIENCE↗

Hanford Double Shell Waste Tank Corrosion Studies (Final Report FY2018)

For FY18, Savannah River National Laboratory (SRNL) focused on four main tasks in its study of corrosion of Hanford Double-Shell Tanks (DSTs). The New Limits task focused on the development of a pitting factor as a localized corrosion predictor. Electrochemical experiments were directed towards pitting factors between 1 and 2 (i.e., borderline conditions) and separating the effects of chloride and fluoride in the pitting factor equation. In addition, long term immersion testing experiments with partial and completely immersed coupons in solutions with a wide range of pitting factors were tested. Secondary liner studies continued this year with a new vapor corrosion inhibition (VCI) strategy in which ground water (GW) simulants at a specified concentration of commercial VCI were mixed. The specific concentrations were recommended by Cortec® and was compared with similar concentration of GW with calcium carbonate. The anodic drift task utilized a simulant corresponding to AN-107 waste tank chemistry. The chemistry was studied with three different surface conditions: mill-scale, partial mill-scale and ground to 600 grit to study the impact of different surfaces on the potential drift. The final task was focused on ammonia concentration determination of a vapor space corrosion (VSC) test vessel using Quartz-Enhanced Photoacoustic Spectroscopy (QEPAS) detector. A summary of each task is presented below.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Well Casing Baseline Analysis for the Bayou Choctaw Strategic Petroleum Reserve Site

This report analyzes data from multi-arm caliper (MAC) surveys taken at the Bayou Choctaw Strategic Petroleum Reserve site to determine baseline statistics for the original innermost cemented casing or the subsequent installed liner. Along with analyzing the internal diameters from the MAC surveys, this analysis looks to approximate casing weight, an important metric for determining the strength of well sections. Casing weight is calculated for each section, survey, and well. Results from the analysis show most wells reflect the dimensions in the original as-built drawings. There are, however, several exceptions. Some well sections have calculated wall thicknesses outside API tolerance. In addition, some well section depths differ from the as-built drawings. All results are discussed on a well-by-well basis. Where applicable, information from this report should be used to update as-built drawings and aid in creating more accurate well models for future studies.

02 PETROLEUM↗

Thermoplastic Composite Compressed Gas Storage (CGS) Tanks

This report summarizes the progress made on utilizing polyamide carbon fiber tapes for composite overwrapped pressure vessels (CPVs) using Automated Fiber Placement (AFP). This project is joint development project run through the Institute for Advance Composite Manufacturing Innovation (IACMI) with DuPont, Steelhead Composites, University of Dayton Research Institute, and the Composites Prototyping Center. Over the course of this program, the Team developed and/or demonstrated the materials and processes that are required to produce vessels for compressed gas storage, including polyamide matrix formulation, unidirectional polyamide/carbon fiber tape production, and automated fiber placement on a vessel liner. In addition, a cost of manufacture analysis was performed that compares Type III and Type IV vessels made with both thermoplastic and thermoset chemistries. This report summarizes the myriad of technical advances made during this project, culminating with production and testing of an aluminum-lined Type III pressure vessel. Each step was optimized locally so as to produce the best material. The end result was a test vessel that, while demonstrating some of the benefits of thermoplastic matrix composites, did not perform as well as those produced by filament winding of carbon fiber/epoxy prepregs. This was most likely due to the Team’s focus on local optimization rather than globally optimizing the entire process from beginning to end. Should further work be contemplated, a more focused effort on global optimization should be pursued.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

EURATOM Fast Collar for BWR (EFCB) Field Calibration Exercise

A neutron collar for the measurement of fresh BWR fuel assemblies (EFCB) has been designed and built by Los Alamos National Laboratory (LANL) and the Euratom Safeguards Directorate (Euratom). The design was similar to a previous collar designed for the measurement of fresh PWR assemblies. A key feature of both of these collars is that they operate in fast mode (preventing the return of thermal neutrons into the assembly by means of a cadmium liner) to reduce the effect of burnable poisons on the measurement. The current report describes the results of the field calibration exercise that was carried out at the ENUSA Fuel Fabrication Plant in Juzbado, Spain from May 28 to May 31, 2019.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Benchmarking 3D-MHD simulations of electrothermal instability growth by studying z-pinches with engineered defects

The electrothermal instability (ETI) is driven by Joule heating and arises from the dependence of resistivity on temperature. ETI may drive azimuthally correlated surface density variations which seed magneto Rayleigh-Taylor (MRT) instability growth. Liner implosion studies suggest that dielectric surface coatings reduce the amplitude of ETI driven perturbations. Furthermore, previous fundamental physics studies suggest that non-metallic inclusions within the metal can seed ETI growth. In this project, we aimed to (1) determine how dielectric coatings modify ETI growth by varying the coating thickness and the surface structure of the underlying metal, and (2) study overheating from engineered defects—designed lattices of micron-scale pits. Engineered pits divert current density and drive local overheating in a way that can be compared with 3DMHD simulations. All experiments were executed on the Sandia Mykonos Facility. Facility and diagnostic investments enabled high quality data to be gathered in support of project deliverables.

42 ENGINEERING↗

Report for Pecos Activities (CY 2019)

All experiments involving the Pecos target chamber in calendar year (CY) 2019 were dedicated to Pre-Heat studies in the context of Magnetized Liner Inertial Fusion (MagLIF). Activities at the target area included actual laser shots but also diagnostic and maintenance, and preparatory work for experiments with cryogenically cooled targets, which are anticipated for CY 2020. Since the Z-Beamlet and Z-Petawatt lasers support multiple campaigns, we can only anticipate laser and laser-operator time for one out of three shot windows in a day, and typically not on every day of the week. For that reason, many of our non-shot activities need to be traded against shots as well.

43 PARTICLE ACCELERATORS↗

w18_plxa Final Report Viewgraphs [Slides]

For our fusion concept, we want to look at the influence of: 1) Density perturbations of the liner [shell that pushes on the target to get the target to fusion conditions] and 2) Magnetic field and anisotropic conductivity effects. On the compression of the target (final ion temperatures, without nuclear reaction calculations)

97 MATHEMATICS AND COMPUTING↗

Energy Efficient Thermoplastic Composite Manufacturing

The objective of the project was to establish an effective and affordable method to lay-up and consolidate/join large thermoplastic composite aerospace structure with cycle times measured in minutes rather than hours. Composite airplane designs have proven efficient and effective however future potential product production rates are challenging what the current systems can efficiently produce due to material lay-down constraints and extended thermal cycle times. The ability to lay-up then rapidly heat, consolidate, and cool large complex composite structures plus very accurately tool them (i.e. matching CTE of composite materials) along with very precise thermal control is a difficult challenge. Current systems such as autoclave processing of thermoset materials require long cycle times due to method of heating and the large associated thermal masses. These extended cycle times inhibit the ability to meet higher rate production scenarios due to the need for multiple sets of equipment and tools. Thermoplastic composite materials were used to facilitate more rapid cycle times via the elimination of a need for a cure dwell at temperature. Also, utilized induction heating along with smart susceptors to enable the quick cycle times needed while providing precise intrinsic thermal control. The intrinsic control of the induction heating process via the smart susceptors along with the use of laser assisted fiber placement were the key innovations areas developed. The ability to rapidly heat and then precisely control the temperature of the consolidation component was paramount to the success of this project. It is this unique processing attribute coupled with the thermoplastic material characteristics along with rapid lay-up methods that are novel and advantageous. While many requirements and influencing factors decide the materials and processes utilized for future airplane construction, the forecast of accelerated production rates and the recent performance successes of composites in airplane construction provide an opportunity for this processing technology to have significant influence. During the course of this project a number of key accomplishments were completed. They are as follows: The needed laser assisted fiber placement capabilities have been developed and validated on a component of meaningful scale and complexity. Subsequently, a thermoplastic preform of the part scale-up part design was laser assisted fiber placed and made availalbe for consolidation. An induction consolidation system was sized, designed, and fabricated resulting in the full capability to consolidate the scale-up component. The tool for induction consolidating of the scale-up component was designed and fabricated. An aluminum pressure bladder was welded and formed for use as the pressurization membrane to perform the needed application of pressure on the part at temperature to achieve consolidation. The induction consolidation system consisting of the restraint, induction power supply, induction tool with integrated induction coils and smart susceptor liners, along with the aluminum bladder were successfully used to consolidate a large thermoplastic skin. The capability of accomplishing rapid heat-up rates and cool down rates for consolidation of large thermoplastic skins with precise thermal control and even pressure application at the consolidation temperature was validated. The general conclusion is that the use of induction consolidation with smart susceptors is an effective method to rapidly and efficiently consolidate large thermoplastic composite components and enable affordable high rate manufacturing of composites. More specific conclusions generated by this project are as follows: A restraint type induction consolidation system provides an affordable option over the standard press when using the induction consolidation processing method. Aluminum bladders can be formed to the complex shapes needed and supply uniform pressure for consolidation and co-consolidation of thermoplastic composite materials. Straightforward modifications can be made to existing fiber placement robotic systems to enable their use for thermoplastic lay-up applications.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗