Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Pattern”

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 1,531 records · Page 85
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Verification Data Pattern Recognition and Change Detection at the Neutron Instrument Level

As the pressure on International Atomic Energy Agency (IAEA) safeguards resources increases, there is a drive to essentially “do more with less.” New ways of using current verification instrumentation and visualizing the collected data are needed, coupled with maintaining and sustaining the current safeguards instrumentation fleet. This paper explores how to innovate with current safeguards neutron instrumentation using data-driven algorithms at the instrument level. A concept is described for upgrading current neutron counting systems with modern electronics by leveraging electronics developments in other fields (e.g., high-energy physics) to facilitate full list mode data acquisition and, therefore, expand existing analyses to pattern recognition and change detection at the instrument level. The aim is to advance correlated neutron counting by improving the reliability of detecting nuclear material diversion and, at the same time, to improve the sustainability of those systems. It is likely that upgrading existing systems with new hardware and software is more cost-effective than replacing systems with other novel systems that might meet this need. A specific project example is highlighted in which a system was upgraded by retrofitting the standard uranium neutron collar detector with new electronics; as a result, verification data can be analyzed in new ways. A new neutron analysis method, the “List Mode Response Matrix,” has been developed to analyze every pulse train from the detector array and thus enable the verification of spatial information about the assay item for safeguards inspections. This project has improved the reliability of resolving individual fuel pin locations within a given fresh fuel assembly and the percentage of partial defects detected. Herein, the overall concept of upgrading current neutron counting systems is discussed with respect to the potential increase in analysis capabilities. In addition, the details and results of the list mode collar project are discussed.

Worrall, Louise G.↗
DOE OSTI2020

Biomolecular patterning of three dimensional tissue scaffolds

The invention provides methods and compositions for making and using collagen-glycosaminoglycan three-dimensional scaffolds immobilized with biomolecules that are spatially and temporally patterned. The method comprises adding benzophenone to a collagen-glycosaminoglycan three dimensional scaffold in the dark; adding one or more biomolecules to one or more areas of the collagen-glycosaminoglycan three-dimensional scaffold (which can be done optionally in the dark or in the light); and exposing the collagen-2glycosaminoglycan three-dimensional scaffold to light at a wavelength of about 350 to about 365 nm.

59 BASIC BIOLOGICAL SCIENCES↗
DOE OSTI2020

Spatiotemporal Pattern Recognition in the PMU Signals in the WECC system

Phasor measurement unit (PMU) data has been used by multiple power system applications, including state estimation, post event analysis, oscillation detection, model validation, and many others. Still, due to its big data nature and availability to general research institutions, comprehensive understanding of the spatiotemporal patterns and underlying mechanisms are incomplete. This study applies a set of signal processing and machine learning approaches aiming at deciphering the characteristic behaviors of multiple phasor measurement units (PMUs) attributes (e.g., voltage, frequency, rate of change of frequency, phase angle), including their auto-correlation, cross-dependence, similarities and discrepancies across units and temporal scales, and distributions of anomalies and their linkages to potential external factors such as weather events. Data analytics are applied to PMUs from the U.S. Western Electricity Coordinating Council (WECC) system. The PMU measurements, recorded events, outages, and weather extremes are all from real world datasets. The findings from the study and mechanistic understanding of the PMU dynamics help provide guidance on system control or preventing blackouts. The derived metrics can be directly used for adjusting or filtering simulated PMU data used for advanced algorithm development.

Hou, Zhangshuan↗
DOE OSTI2019

Trends and Patterns in the Evolving Threat to Radioactive and Nuclear Material Transportation

Roughly 20 million shipments of radioactive material are transported worldwide each year via commercial transportation vectors. Many of these can be considered a significant movement of risk-significant quantities of radioactive and nuclear material. A strong argument can be made to support the idea that transportation presents the greatest vulnerability in radioactive sealed source and nuclear material life-cycles. Historical and current information strongly suggests adversarial interest in obtaining radiological and nuclear materials with the intent of malicious use. In this context, it is necessary to understand the current trends and patterns in transportation threats as they apply to these materials in order to better understand security needs and current adversarial methods and mind-set.The authors propose to summarize current threats posed to radiological and nuclear materials during the transportation phase of the lifecycle. The paper and ensuing presentation will focus on a review of historical events where the adversarial intent was to disrupt the transportation phase of nuclear and radioactive material with malicious intent, as reported in open source literature. Its purpose is to better understand the nature of current and past transportation incidents involving these materials in order to clarify the evolving nature of the threats and vulnerabilities they reveal. Relevant incidents involving transportation of these materials will be discussed as well as the historical trends associated with these events. A regional perspective based on an analysis of transportation incidents involving these materials will be discussed. While not necessarily predictive of the types of malicious disruptions that might occur in the future, this study will provide a rich information source from which lessons can be gleaned pertinent to the potential security and public safety threats posed by the transportation of commercial radioactive and nuclear material.

Shannon, Michael↗
DOE OSTI2023

Self-Assembled Monolayer Procedure to Pattern Silicon Passivated Contacts

We utilize hexamethyldisilazane (HMDS)-based self-assembled monolayers to pattern polysilicon (polySi) passivated contacts. We find process conditions that allow for etching frontside n/polySi between fingers, thereby increasing Jsc. Importantly, the Voc does not degrade indicating the additional process steps do not introduce defects or impurities. HMDS layers remain on the surface for metallization without detriment to transport.

hexamethyldisilazane↗
DOE OSTI2023

Multimaterial powder bed patterning for additive manufacturing method

The present disclosure relates to an additive manufacturing system. In one embodiment the system makes use of a reservoir for holding a granular material feedstock. A nozzle is in communication with the reservoir for releasing the granular material feedstock in a controlled fashion from the reservoir to form at least one layer of a part. An excitation source is included for applying a signal which induces a controlled release of the granular material feedstock from the nozzle as needed, to pattern the granular material feedstock as necessary to form a layer of the part.

Dudukovic, Nikola↗
DOE OSTI2016

Channel Bow Constraint Option in the BWR Loading Pattern Optimization System FINELOAD-3

The boiling water reactor (BWR) loading pattern (LP) optimization system FINELOAD-3 (FL3), has been applied for actual BWR reload core design for over fifteen years in TEPCO Systems Corporation (TEPSYS) and for over ten years in several European utilities. FL3 works in combination with the advanced nodal core simulator SIMULATE-3 (S3) or other core simulators. Recently, the channel bow constraint option has been added in FL3. In the BWR reload core design work, the channel bow management is very important in order to avoid the interference between a channel and a control blade and/or to minimize the effect on critical power ratio during the operation cycle. The channel bow constraint option is applied to eliminate channel bow violation against design target. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2024

PV Modules Temperature Variation and Patterns in Medium and Utility-Scale Floating PV Systems

This paper presents the preliminary results and findings of the four operational Floating PV systems across the USA. At each site, temperature of five PV modules located at North-West, North-East, Middle, South-West, and, South-East have been monitored through the Resistant Temperature Detector (RTD) sensors. Three RTDs were attached to each PV module on the rear-side along the diagonal at top, middle and bottom cells. The preliminary results reveal wide temperature differences among the inter and intra PV modules. Besides this, wave pattern temperatures were observed in a few PV modules. The final results, findings, and, factors responsible will be investigated during the next few months. Index Terms - photovoltaic module, floating PV systems, string, array, temperature, mismatch, utility scale.

ENGINEERING,SOLAR ENERGY↗
DOE OSTI2022

Multiscale spatial analysis of fracture arrangement and pattern reconstruction using Ripley's K-function

This work presents novel multiscale spatial data analytics using Ripley's K-function, as a measure of spatial interaction, to study one-dimensional arrangement of fractures. Fracture spatial arrangements are classified into clustered, anticlustered, or indistinguishable from random by testing statistical significance of the calculated Ripley's K-function. Characterizations of fracture arrangements are performed as a function of length scale and position. Analysis of the K-function along the study interval identifies where fracture clustering and anticlustering occur. Here, a simulation technique is also introduced here to statistically reconstruct spatial arrangements and to generate fracture realizations that are spatially similar to the fractures observed in the field. With this simulation technique, one can also fill spatial gaps in fracture measurements where data are absent, unreliable, or unused. Synthetic as well as field-measured 1D fracture datasets are used for testing and demonstration. Methods introduced in this work can be readily applied to fracture datasets observed in outcrops, borehole image logs, and cores.

58 GEOSCIENCES↗
DOE OSTI2018

A deterministic method for PWR loading pattern optimization

A new deterministic approach to core loading optimization is presented. Selection of fuel enrichment and burnable poison (BP) arrangement in a pressurized water reactor (PWR) core are optimally determined subject to power peaking factor (PF) constraints. The deterministic approach is based on the method of Lagrange multipliers and the direct adjoining approach for the inequality power PF constraint. The optimality conditions are derived using calculus of variations resulting in the presence of jump conditions and a linear control Hamiltonian. The optimal control problems are addressed by simultaneously minimizing the Hamiltonian using the gradient method and performing Newton's method in different regions of the core to produce viable solutions for the controls. Without active control of the power profile in PWRs during depletion, our methodology is able to satisfy the power PF constraint at all times by proper loading selection at the beginning of cycle (BOC). This is achieved by promoting the proper burnup path forward in time during the calculation of the forward optimality conditions. Here this information is utilized in the adjoint burnup calculation, which acts to propagate the optimal control path back to the BOC during the calculation of the adjoint optimality conditions. The methodology has been developed into a new code DMCO (Deterministic Multi-Control Optimization) which can produce two-dimensional two-group depletion results in approximately seven minutes per optimization iteration on a personal computer. No application of heuristics is required and the code is capable of finding solutions from initial control distributions. A preliminary case study is presented for the Westinghouse AP600 first cycle fuel loading design which achieved an extended fuel cycle while satisfying power PF constraints.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2026

Optimizing pressurized-water reactor equilibrium cycle using a novel loading pattern encoding and rule-based genetic crossover operators

This work presents an extended multi-batch approach applied in shuffling scheme optimization for equilibrium cycle for pressurized water reactors using Genetic Algorithms (GAs). A new ruled based GA crossover operator called Inherited Location and Batch (ILB) was introduced to enhance offsprings reproduction efficiency specialized for equilibrium cycle optimization problem. This approach was implemented within the Plant ReLoad Optimization (PRLO) framework and validated using a generic reactor model based on the AP1000 design, with core parameters calculated via the CASMO/SIMULATE software package. The ILB approach is then applied for both single and multi-objective problems in maximizing cycle length and core average exposure while minimizing the average enrichment of the 57 fresh fuel assemblies (FAs) per cycle. The optimal solutions are selected based on their dominance to the objectives from all feasible solutions. This research identified three optimal solutions satisfied safety constraints: The first solution minimizes feed enrichment costs with a cycle length of 338.8 days and core exposure of 25.39 MWd/MT; the second solution extends cycle length to 361.2 days, with the highest core exposure of 26.84 MWd/MT, using 3.75 wt% average fuel enrichment; the third solution balances both objectives with a cycle length of 349.6 days, core exposure of 25.82 MWd/MT with a slight enrichment increase compared to the first solution. Collectively, these findings underscore the efficiency and effectiveness of the proposed approach in achieving practical multi-objective optimal equilibrium cycle designs using GAs optimizer.

11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗