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At least 361 records · Page 20
All sourcesNASA NTRSDOE OSTI
DOE OSTI2019

Impact of CSPE Jackets on Accelerated Aging of Harvested Cable Insulations in Support of Remaining Useful Life Assessments

Nuclear power plants (NPPs) are operating beyond their original 40-year operating lifetime, with more than 80% operating on the first license renewal for an extended 20-years. To sustain the effective and cost-effective operation of their electrical cables, understanding cable material performance in current and future environments can lead to effective maintenance strategies and condition monitoring protocols. Addressing the issue of long-term operation and viability, accelerated aging was carried out on chlorosulfonated polyethylene (CSPE) / ethylene propylene rubber (EPR) insulations that were removed from harvested electrical cables. Cables were obtained as part of the Light Water Reactor and Sustainability (LWRS) Zion Harvesting Project in cooperation with Energy Solutions and the U.S. NRC. Zion NPP was in operation for 25 years prior to decommissioning before its 40-year operation license had expired.For the Boston Insulated Wire (BIW) manufactured EPR insulation with outer CSPE jackets, degradation was observed in mechanical properties with respect to time and temperature was observed. This degradation was impacted by the outer CSPE jacket as the increase in to the time to degradation at the same temperature was observed for EPR insulations with the outer CSPE jacket removed prior to aging. The correlation of IM and density to EAB also suggested that these parameters could also be used effectively in the estimates of activation energy with additional data. Arrhenius analysis on the mechanical degradation as measured by EAB for the two types of BIW EPR insulations with outer CSPE jackets estimated activation energies slightly different (BIW-A without outer CSPE jacket 1.58 eV, BIW-B with outer CSPE jacket 1.10 eV) than the 1.24 eV found in from analysis of EAB data found in Zion NPP BIW insulation documentation. These values were higher than those previously reported of 0.90 eV to 0.96 eV for CSPE and EPR materials in the literature and additional measurements are needed to further validate the increase in activation energy for these harvested materials and possible impact on remaining useful life estimation. Finally, FTIR analysis showed differences in the oxidation as measured by decrease in C-H bonds in EPR insulation and CSPE jackets and increase in C-O bonds in certain cases.

Davis, Sarah M.↗
DOE OSTI2018

Nondestructive Testing Research and Capabilities at Pacific Northwest National Laboratory

Pacific Northwest National Laboratory (PNNL) is a United States Department of Energy (DOE) multipurpose laboratory operated by Battelle Memorial Institute. The laboratory maintains several technical and scientific capabilities to meet the diverse and challenging needs of sponsors. The Applied Physics Group maintains significant capabilities of interest to the nondestructive testing (NDT) community and regularly collaborates with other technical disciplines to form unique teams in response to specific challenges. This article provides a brief overview of the capabilities of the Applied Physics Group and highlights some activities to demonstrate the scope of capabilities that span from applied research aimed at improving existing NDT methods or processes to more fundamental research efforts that are focused on developing tools to facilitate future paradigms of structural condition monitoring and awareness.

Nondestructive Testing, NDE, Nuclear Power, Phased↗
DOE OSTI2015

Progress in the Investigation of Nuclear Power Plant Cable Aging

The thousands of miles of polymer-insulated cables used for power, control and communications in nuclear power plants were originally qualified for forty years of plant operation. Continued use of cable in existing plants for periods much beyond their original qualified life will require a detailed understanding of cable degradation under plant operating conditions to assess and mitigate risk of continued use. The effect and relative importance of individual and combined environmental stresses including radiation, heat and moisture on reliable cable performance is essential to inform condition monitoring, lifetime prediction and required cable replacement planning. We present an overview and update of the nuclear cable aging program at the Pacific Northwest National Laboratory and the Oak Ridge National Laboratory supported by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability program

Fifield, Leonard S.↗
DOE OSTI2015

PROGRESS IN THE INVESTIGATION OF NUCLEAR POWER PLANT CABLE AGING

The thousands of miles of polymer-insulated cables used for power, control and communications in nuclear power plants were originally qualified for forty years of plant operation. Continued use of cable in existing plants for periods much beyond their original qualified life will require a detailed understanding of cable degradation under plant operating conditions to assess and mitigate risk of continued use. The effect and relative importance of individual and combined environmental stresses including radiation, heat and moisture on reliable cable performance is essential to inform condition monitoring, lifetime prediction and required cable replacement planning. We present an overview and update of the nuclear cable aging program at the Pacific Northwest National Laboratory and the Oak Ridge National Laboratory supported by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability program.

cable, insulation, polymer, EPR, XLPE, aging, degr↗
DOE OSTI2018

State of Electrical Cable Aging in U.S. Nuclear Power Plants

Nuclear energy has supplied one fifth of the electricity generation in the United States for the last thirty years, but headwinds for continued contribution of nuclear to the US energy mix include the aging state of existing plants and the challenge of remaining cost competitive with energy alternative such as natural gas. As an integral component of the power, control and safety operations of a nuclear power plant, electrical cables are a significant factor in both long term and resource-efficient plant operation. The cost and practical challenge of wholesale replacement of the thousands of miles of cables in each reactor make effective management of the existing cable inventory increasingly important as the cables age in service. Total generation costs for US nuclear reactors have increased in the last decade, due in part to safety and security upgrades. Passive, long-lived structures, systems and components may be subject to aging-related degradation, necessitating increase frequency of inspection and repair/replace decisions. Costs associated with cable aging management in long-term operation can be reduced with effective cable condition monitoring technology and sufficient understanding of material aging behavior. Technical basis for confidence in cable status can reduce the frequency of cable system inspections and align cable replacement decisions with physical need. Knowledge of cable remaining useful life can allow longer term cable maintenance planning and fewer unplanned outages. As methods for relating measurable key indicators of aging with cable status develop, industry has begun to demonstrate how informed cable aging management can help to minimize costs necessary for safe, long-term operation.

light water reactors, electrical cables, nuclear p↗
DOE OSTI2022

Integrated Risk-Informed Condition Based Maintenance Capability and Automated Platform: Technical Report 3

This project is a collaborative research effort between PKMJ Technical Services LLC, Idaho National Laboratory, and Public Service Enterprise Group (PSEG) Nuclear, LLC. The collaboration, led by PKMJ Technical Services LLC, is part of the industry Funding Opportunity Announcement (FOA) award under Advanced Nuclear Technology Development FOA #DE-FOA-0001817. The pilot demonstration focuses on the Circulating Water System (CWS), an important non-safety-related system that impacts the power generation capability of the plant site. Achieving riskinformed condition-based Predictive Maintenance (PdM) on the CWS will result in significant economic benefits, and the developed methodologies can also be applied to other plant systems. This approach supports an industry goal of ensuring that nuclear power generation remains a viable, economically competitive option in the energy market. Operation and Maintenance (O&M) costs include labor-intensive Preventive Maintenance (PM) programs that involve manually performed inspection, calibration, testing, and maintenance of plant assets at periodic frequencies as well as time-based replacement of assets, irrespective of condition. This project offers an alternative by focusing on riskinformed condition-based maintenance to reduce O&M costs while still maintaining plant health and safety. This report summarizes the progress made toward achieving a risk-informed condition-based maintenance approach. The research and development (R&D) activities presented in this report are associated with development of a nuclear digital platform application, integration of fault signature models, and automated work management processes. The fault signatures and Machine Learning (ML) models are key components in predictive analytics and are heavily leveraged to improve the insights received by existing plant process data sources. Availability of the analysis results within a centralized digital platform enhances efficiency by enabling automation of activities otherwise performed manually. Personnel are presented with enhanced information that can be used to evaluate plant status and risks. Utilizing the enhancements to data analytics supports automated responses, (i.e. issuance of work orders) to address developing equipment faults and thus preventing forced, unplanned shutdowns of components or systems. The R&D activities described within this report lay the foundation for developing and demonstrating a digital automated platform to centralize the implementation of condition monitoring and response to equipment faults. The digital automated platform is cloud-based and designed to enable improved efficiency of plant processes. The digital platform includes content related to maintenance optimization, fault signature analysis, and plant records, which can all be used to support efficiencies when located within a centralized digital platform. These efficiencies could be further enhanced when deployed through industry-wide deployment of the technology to improve insights and processes based upon economies of scale.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2015

Bare Fiber Bragg Gratings embedded into concrete buffer Supercontainer concept for nuclear waste storage [ANIMMA--2015-IO-337]

Nuclear power plants have been generating electricity for more than 50 years. In Belgium, 55% of the current energy supply comes from nuclear power. Providing for the safe storage of nuclear waste, including spent fuel (SF) and vitrified high level radioactive waste (HLW), remains an important challenge in the life cycle of nuclear fuel. In this context, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) is investigating a reference conceptual design called the Supercontainer (SC) for the packaging of SF and HLW. This conceptual design is based on a multiple-barrier system consisting of a hermetically-sealed carbon steel overpack and a surrounding highly-alkaline concrete buffer. The first one is developed to retain the radionuclides. The two main functions of the buffer are (a) to create a high pH environment around the carbon steel overpack in order to passivate the metal surface and so to slow down the corrosion propagation during the thermal phase and (b) to provide a radiological shielding during the construction and the handling of the Supercontainer. A recent test has been performed to investigate the feasibility to construct the SC. This test incorporated several kinds of sensors including Digital Image Correlation (DIC), Acoustic Emission (AE), corrosion sensing techniques and optical fibers with and without fiber Bragg gratings (FBGs). In particular, several single-mode optical fibers with 4 mm long FBGs with different Bragg wavelengths and distributed along the optical fibers were used. For casting and curing condition monitoring, a number of gratings were incorporated inside the concrete buffer during the first stage of construction. Then other sensors were embedded near a heat source installed in the second stage to simulate the effects of heat generated by radioactive waste. The FBGs were designed to measure both temperature and strain effects in the concrete. To discriminate between these effects special packaging was used for some sensors that were installed very close to the unpackaged ones. Sensors placed in plastic tubes have reduced sensitivity to strain, while the ones inserted in metal tubes are only temperature sensitive and their readings can be directly compared with those obtained from thermocouples located nearby. In addition to monitoring temperature and strain behaviour, embedding also had as objective to determine the impact of the high alkaline environment on the silica fibers over a very long time. This article presents the preliminary results obtained with the different FBGs and provides recommendations for future improvement. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Inspection Technologies for Waste Containers at Canadian Nuclear Laboratories - 19429

To provide data for aging management programs, containers for different forms of nuclear waste, ranging from low-level waste to irradiated nuclear fuel, should be inspected. At Canadian Nuclear Laboratories, visual, ultrasonic, electromagnetic, and hybrid forms of non-destructive evaluation (NDE) are used for in situ inspection of carbon steel containers having various configurations, access issues, and material thickness. NDE applications tailored to the requirements of the task provide data for condition monitoring and operational assessments. The examples of fuel baskets stacked in concrete canisters and sheet metal containers arrayed in warehouses are illustrated here. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2025

Luminosity measurement for lead-lead collisions at $\sqrt{s_{\mathrm{NN}}}$ = 5.02 TeV in 2015 and 2018 at CMS

Measurements of the luminosity delivered to the CMS experiment during the lead-lead data-taking periods in 2015 and 2018 are presented for the first time. The collisions were recorded at a nucleon-nucleon center-of-mass energy of 5.02 TeV; the 2018 data sample is three times larger than the 2015 data sample. Three subdetectors are used: the pixel luminosity telescope, the forward hadron calorimeters, and the fast beam conditions monitor. The absolute luminosity calibration is determined using the van der Meer technique that relies on transverse beam separation scans. The dominant sources of uncertainty are the transverse factorizability of the bunch density profiles and, in 2015, the difference between the results obtained using various detectors. The total uncertainty in the integrated luminosity, including the stability of the calibrated subdetector response over time, amounts to 3.0% for 2015, 1.7% for 2018, and 1.6% for the combined data sample.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2024

Smart indoor air venting system

A venting system in accordance with the present disclosure includes a ventilation fan and one or more sensors coupled to the ventilation fan. The ventilation fan is positioned to vent air from an indoor environment. The sensors are positioned to monitor conditions in the indoor environment and selectively operate the ventilation fan to condition air in the indoor environment.

Moore, Mike↗
DOE OSTI2013

Incorporating Equipment Condition Assessment in Risk Monitors for Advanced Small Modular Reactors

Advanced small modular reactors (aSMRs) can complement the current fleet of large light-water reactors in the USA for baseload and peak demand power production and process heat applications (e.g., water desalination, shale oil extraction, hydrogen production). The day-to-day costs of aSMRs are expected to be dominated by operations and maintenance (O&M); however, the effect of diverse operating missions and unit modularity on O&M is not fully understood. These costs could potentially be reduced by optimized scheduling, with risk-informed scheduling of maintenance, repair, and replacement of equipment. Currently, most nuclear power plants have a “living” probabilistic risk assessment (PRA), which reflects the as-operated, as-modified plant and combine event probabilities with population-based probability of failure (POF) for key components. “Risk monitors” extend the PRA by incorporating the actual and dynamic plant configuration (equipment availability, operating regime, environmental conditions, etc.) into risk assessment. In fact, PRAs are more integrated into plant management in today’s nuclear power plants than at any other time in the history of nuclear power. However, population-based POF curves are still used to populate fault trees; this approach neglects the time-varying condition of equipment that is relied on during standard and non-standard configurations. Equipment condition monitoring techniques can be used to estimate the component POF. Incorporating this unit-specific estimate of POF in the risk monitor can provide a more accurate estimate of risk in different operating and maintenance configurations. This enhanced risk assessment will be especially important for aSMRs that have advanced component designs, which don’t have an available operating history to draw from, and often use passive design features, which present challenges to PRA. This paper presents the requirements and technical gaps for developing a framework to integrate unit-specific estimates of POF into risk monitors, resulting in enhanced risk monitors that support optimized operation and maintenance of aSMRs.

Advanced Small Modular Reactors↗
DOE OSTI2022

Miniature Crack or Damage Detection on Cable Insulation and Jacket Using Conformal Surface Wave Reflectometry

This letter introduces the study and application of a conformal surface wave launcher array to detect miniature insulation and/or jacket damage on unshielded cables. Here simulation and experimental results are presented that demonstrate that with the proposed concept very small instances of damage at various distances along power cables can be detected. Effects of damage detection feasibility in the presence of other cables in proximity and for cables containing semiconducting screen are also presented.

42 ENGINEERING↗
NASA NTRS2010

Exploiting the Free Landsat Archive for Operational Monitoring of Ecosystem Condition and Change Across the Chesapeake Bay Watershed

For the first time, all imagery acquired by the Landsat series of satellites is being made available by the USGS to users at no cost. This represents a key opportunity to use Landsat in a truly operational monitoring framework: large regions of the U.S. such as the Chesapeake Bay Watershed can now be analyzed using "wall-to-wall" imagery at timescales from approximately 1 month to several years. With the future launch of the Landsat Data Continuity Mission (LDCM) and Decadal Survey missions such as the hyperspectral HyspIRI, it is imperative to develop robust processing systems to perform annual ecosystem assessments over large regions such as the Chesapeake Bay. We have been working at NASA's Goddard Space Flight Center (GSFC) to develop an integrative framework for inserting 30m, annual, Landsat based data and derived products into the existing decision support system for the Bay, with a particular focus on ecosystem condition and changes over the entire watershed. The basic goal is to use a 'stack' of Landsat imagery with 40% or less cloud cover to produce multi-date (2005-2009 period), cloud/shadow/gap-free composited surface reflectance products that will support the creation of watershed scale land cover/ use products and the monitoring of ecosystem change across the Bay. Our scientific focus extends beyond the conventional definition of land cover (i.e. a classification of vegetation type) as we propose to monitor both changes in surface type (e.g. forest to urban), vegetation structure (e.g. forest disturbance due to logging or insect damage), as well as winter crop cover. These processes represent a continuum from large, interannual changes in land cover type, to subtler, intra-annual changes associated with short-term disturbance. The free Landsat data are being processed to surface reflectance and composited using the existing Landsat Ecosystem Disturbance Adaptive Processing System here at NASA/ GSFC, and land cover products (type, tree cover, impervious cover, winter cover) are being produced using well-established decision tree and regression tree algorithms. The goal of this session is to present the data products that we have been developing to the Bay science community and to discuss potential avenues for improvements and usage of the products for decision support.

BrowndeColstoun, Eric↗
DOE OSTI2025

Optical Fiber Sensor with a Hydrophobic Filter Layer for Monitoring Hydrogen under Humid Conditions

Real-time and remote monitoring of hydrogen concentration in underground hydrogen storage reservoirs is crucial to maintaining the integrity and safety of the storage facilities. High humidity in the underground deposits interferes with hydrogen sensors, introducing inaccuracy into the hydrogen sensing measurements. A hydrophobic filter layer over a hydrogen sensing layer on an optical fiber hydrogen sensor was devised to minimize the impact of the humidity on the sensor. The hydrogen sensor coated with a hydrophobic filter layer demonstrated a significant improvement in reliable hydrogen sensing under high humidity conditions (99% RH) without severe baseline drift and reduction of transmission intensity. Finally, the optical fiber hydrogen sensor revamped with the filter layer would enable the reliable measurement of hydrogen concentration under the humid conditions expected in subsurface hydrogen storage facilities.

08 HYDROGEN↗
DOE OSTI2019

Second Annual Progress Report on Ultrasonic Sensors for TREAT Fuel Condition Measurement and Monitoring

Fuel deformation (both axial and radial) information provides insights into fuel performance and failure limits. Traditionally, fuel deformation has been quantified using post-irradiation examinations due to the lack of an appropriate sensor for monitoring deformation in situ. Recent developments in sensor and instrumentation design have led to the use of linear variable differential transformers (LVDT) for monitoring axial strain in fuel during irradiation. Size and operational constraints limit the use of LVDT sensors for radial deformation monitoring, and alternatives are needed. One possible alternative to LVDT sensors is an ultrasonic sensor. Ultrasonic sensors monitor the interaction of high-frequency stress waves with the test object. The resulting response may be analyzed to determine the properties of the material, including stress, strain, microstructure, presence of defects, and the elastic constants. While ultrasonic measurements have been successfully applied for monitoring strain in a number of applications, their use for in-core measurements has been limited. Largely, the limitations are due to the challenges associated with designing sensors that can operate under typical in-core conditions. The overall objective of this work is to design an ultrasonic sensor capable of rapid in-situ measurements of fuel rodlet dimensional changes during TREAT transient irradiation testing. This report summarizes the activities and research findings through the end of Year 2 of this three-year project.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
NASA NTRS1992

Monitoring of environmental conditions in the Alaskan forests using ERS-1 SAR data

Preliminary results from an analysis of the multitemporal radar backscatter signatures of tree species acquired by European Remote Sensing Satellite (ERS-1) synthetic aperture radar (SAR) data are presented. Significant changes in radar backscatter are detected. Correlation of these differences with ground truth observations indicate that these are due to changes in soil and liquid water content as a result of freeze/thaw events. C-band observations acquired by the NASA/Jet Propulsion Laboratory Airborne SAR (JPL AIRSAR) instrument demonstrate the potential of a C-band radar instrument to monitor drought/flood events. The potential of ERS-1 for monitoring phenologic changes in the forest and for classifying tree species is less promising.

Rignot, Eric↗
DOE OSTI2013

Methods for improved forewarning of condition changes in monitoring physical processes

This invention teaches further improvements in methods for forewarning of critical events via phase-space dissimilarity analysis of data from biomedical equipment, mechanical devices, and other physical processes. One improvement involves objective determination of a forewarning threshold (U.sub.FW), together with a failure-onset threshold (U.sub.FAIL) corresponding to a normalized value of a composite measure (C) of dissimilarity; and providing a visual or audible indication to a human observer of failure forewarning and/or failure onset. Another improvement relates to symbolization of the data according the binary numbers representing the slope between adjacent data points. Another improvement relates to adding measures of dissimilarity based on state-to-state dynamical changes of the system. And still another improvement relates to using a Shannon entropy as the measure of condition change in lieu of a connected or unconnected phase space.

47 OTHER INSTRUMENTATION↗
DOE OSTI2013

Methods for forewarning of critical condition changes in monitoring civil structures

Sensor modules (12) including accelerometers (20) are placed on a physical structure (10) and tri-axial accelerometer data is converted to mechanical power (P) data (41) which then processed to provide a forewarning (57) of a critical event concerning the physical structure (10). The forewarning is based on a number of occurrences of a composite measure of dissimilarity (C.sub.i) exceeding a forewarning threshold over a defined sampling time; and a forewarning signal (58) is provided to a human observer through a visual, audible or tangible signal. A forewarning of a structural failure can also be provided based on a number of occurrences of (C.sub.i) above a failure value threshold.

47 OTHER INSTRUMENTATION↗