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At least 847 records · Page 47
All sourcesNASA NTRSDOE OSTI
NASA NTRSDate not supplied

The Impact of Dry Intrusions on Midlatitude Cold-Air Outbreak Cloud Transitions

Cold-air outbreaks (CAOs) form marine boundary layer (MBL) clouds that undergo rapid overcast-to-broken cloud regime transitions, initiated by substantial rain. CAOs are usually accompanied by dry intrusions (DIs) that subside as free-tropospheric (FT) air into the postfrontal sector of mid-latitude storms. For an exemplary cold-air outbreak in the NW Atlantic that showed faster transitions (corresponding to reduced extents of overcast clouds) closer to the low-pressure system, we posit that varying transitions are caused by an uneven meteorological pattern imposed by the prevailing DI. We compile satellite observations, reanalysis fields, and Lagrangian large-eddy simulations (LES) translating along MERRA2-based trajectories to show that postfrontal trajectories closer to the low-pressure system are uniquely favorable to rain formation (and, thus, cloud transitions) as they show (1) weaker FT subsidence rates, (2) greater FT humidity, (3) greater MBL windspeeds, and (4) a colder MBL as well as reduced lower-tropospheric stability. We present an updated conceptual view of postfrontal cloud formation that may guide future investigations.

Cold-air outbreaks↗
NASA NTRSDate not supplied

Automated Ply-By-Ply Lamination and in-Situ Consolidation of Dry Carbon Fiber Non-Crimp Fabrics for High-Rate Aircraft Manufacturing of Structural Aircraft Components

NASA’s Hi-Rate Composites Aircraft Manufacturing (HiCAM) program addresses market needs to advance structural aircraft composite manufacturing technologies to significantly increase production rates. Dry, non-crimp fabric (NCF) carbon materials infused with advanced resin systems offer a promising solution to these manufacturing demands. Northrop Grumman’s Automated Stiffener Forming (ASF) technology has been adapted for ply-by-ply, in-situ processing of NCF materials. The modular ASF process accommodates flexibility in the laminate stacking, while allowing for ply drops, ply additions, and yaw, pitch, and roll in the laminate geometry. To adapt the ASF process for NCF materials, heating technologies and roller compaction processes were designed and tested on representative structural aircraft part geometries. Key success criteria for the ASF process with NCF materials is forming quality and preform compaction. Trials were performed with multiple NCF materials: unidirectional up to quad-axial formats. The NCF constituents, veils, stitching, and binders, were evaluated with the ASF process. The material performance in the ASF process and the resulting preform quality are presented.

dry carbon fiber materials↗
NASA NTRSDate not supplied

Automated Ply-By-Ply Lamination and in-Situ Consolidation of Dry Carbon Fiber Non-Crimp Fabrics for High-Rate Aircraft Manufacturing of Structural Aircraft Components

NASA’s Hi-Rate Composites Aircraft Manufacturing (HiCAM) program addresses market needs to advance structural aircraft composite manufacturing technologies to significantly increase production rates. Dry, non-crimp fabric (NCF) carbon materials infused with advanced resin systems offer a promising solution to these manufacturing demands. Northrop Grumman’s Automated Stiffener Forming (ASF) technology has been adapted for ply-by-ply, in-situ processing of NCF materials. The modular ASF process accommodates flexibility in the laminate stacking, while allowing for ply drops, ply additions, and yaw, pitch, and roll in the laminate geometry. To adapt the ASF process for NCF materials, heating technologies and roller compaction processes were designed and tested on representative structural aircraft part geometries. Key success criteria for the ASF process with NCF materials is forming quality and preform compaction. Trials were performed with multiple NCF materials: unidirectional up to quad-axial formats. The NCF constituents, veils, stitching, and binders, were evaluated with the ASF process. The material performance in the ASF process and the resulting preform quality are presented.

dry carbon fiber materials↗
DOE OSTI2014

Eddy Current for Sizing Cracks in Canisters for Dry Storage of Used Nuclear Fuel

The storage of used nuclear fuel (UNF) in dry canister storage systems (DCSSs) at Independent Spent Fuel Storage Installations (ISFSI) sites is a temporary measure to accommodate UNF inventory until it can be reprocessed or transferred to a repository for permanent disposal. Policy uncertainty surrounding the long-term management of UNF indicates that DCSSs will need to store UNF for much longer periods than originally envisioned. Meanwhile, the structural and leak-tight integrity of DCSSs must not be compromised. The eddy current technique is presented as a potential tool for inspecting the outer surfaces of DCSS canisters for degradation, particularly atmospheric stress corrosion cracking (SCC). Results are presented that demonstrate that eddy current can detect flaws that cannot be detected reliably using standard visual techniques. In addition, simulations are performed to explore the best parameters of a pancake coil probe for sizing of SCC flaws in DCSS canisters and to identify features in frequency sweep curves that may potentially be useful for facilitating accurate depth sizing of atmospheric SCC flaws from eddy current measurements.

dry storage↗
DOE OSTI2016

Ultrasonic Clothes Drying Technology

Oak Ridge National Laboratory researchers Ayyoub Momen and Viral Patel demonstrate a direct contact ultrasonic clothes dryer under development by ORNL in collaboration with General Electric (GE) Appliances. This novel approach uses high-frequency mechanical vibrations instead of heat to extract moisture as cold mist, dramatically reducing drying time and energy use. Funding for this project was competitively awarded by DOE’s Building Technologies Office in 2014.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2017

Dry Cask Re Mix HD

Idaho National Lab researchers discuss the Dry Cask Monitoring and Inspection Methods.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2019

Effect of Deposition Temperature on the Tribology of MOCVD Zinc Oxide Thin Films Tested under Dry Contact

Zinc oxide has justifiably been attracting attention in several fields, and the relatively new field of tribology is not left out. Aside from its already extensively researched and documented applications in materials science, semiconductor and electronics industry, zinc oxide nanoparticles and thin films appear to be gaining fast grounds as tribological materials, thereby justifying a zealous approach in further exploring their inherent properties in this area. In this work, zinc oxide thin films were deposited by MOCVD (metal-organic chemical vapour deposition) on soda lime glass andAISI304L stainless steel plates at temperatures of 300°C, 330°C, 360°C, 390°C and 420°C respectively, using anhydrous zinc acetate as the precursor. The carrier gas was air with a flow rate of 2.5 dm 3 min -1 at atmospheric pressure, and deposition time of 2 hours each. The thickness and tribological properties of the thin films produced were thereafter investigated. The thickness was measured by RBS (Rutherford backscattering spectroscopy) using a 1.7 MeV Tandem Accelerator, and the friction and wear properties were tested with a HFRR (high frequency reciprocating rig) under dry contact conditions, Olympus BH-2 Optical Microscope, and ADE Phase Shift MicroXam Optical Surface Profiler. The thickness was found to decrease with increasing deposition temperature, although for the 300°C deposition temperature there appeared to be a bloated thickness, which is attributable to such factors as incomplete precursor decomposition, turbulence in precursor flow, and energy straggling during RBS measurement. The friction tests highlighted coefficients of friction which were relatively low at the onset of the tests, but thereafter rapidly increased, owing possibly to temperature rise, attendant rapid oxidation and aided abrasion by worn debris. The average coefficient of friction of each test was computed, and the outcome (0.33 – 0.43) for all of them was a material still good enough for use in reducing friction at nanolevel, even with worn out matter and increased working temperature, with no noticeable trend regarding their varied deposition temperatures. Microscope and profilometer profiles vividly showed wear scars with material removal and material transfer. The average wear scar diameters as well as the wear volumes were compiled for both the test balls and the thin films. The result showed a largely correlated trend in the wear scar diameters and the wear volumes, and the thin film deposited at 330°C was the coating with the least wear scars, material removal cum transfer on the test ball and sample. This result is attributed to the enhanced thickness of the sample over the others, apart from sample X1 earlier reported to have a problem in its thickness. As a result, this temperature is therefore recommended as the optimum deposition temperature for the best tribologically applicable zinc oxide thin films, using zinc acetate precursor by MOCVD.

36 MATERIALS SCIENCE↗
DOE OSTI2020

DOE EM Sponsored Research on Long-Term Dry Storage of Aluminum Clad SNF

This PowerPoint presentation describes and discusses DOE EM and INL lead studies on addressing potential technical issues associated with long-term dry storage of aluminum clad spent nuclear fuel. This same presentation was made to the US Nuclear Waste Technical Review Board in Nov 2019.

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DOE OSTI2020

ASNF Engineering Scale Drying Experiment Acceptance Criteria for Fabricated Items

This document specifies the acceptance criteria for items fabricated by Holtec International under the scope of INL Contract # 215725, consistent with the parameters described in INL/EXT-19-56017, Aluminum-clad Spent Nuclear Fuel Engineering Scale Drying Experiment Design. Verification is confirmed with initials (or the need for remediation may be identified) along with the date of inspection for each requirement. Verification may be performed by independent proxy (University of South Carolina participant, under INL Contract Number 207046) or by an INL employee, remotely by camera images.

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DOE OSTI2013

US NRC-Sponsored Research on Stress Corrosion Cracking Susceptibility of Dry Storage Canister Materials in Marine Environments - 13344

At a number of locations in the U.S., spent nuclear fuel (SNF) is maintained at independent spent fuel storage installations (ISFSIs). These ISFSIs, which include operating and decommissioned reactor sites, Department of Energy facilities in Idaho, and others, are licensed by the U.S. Nuclear Regulatory Commission (NRC) under Title 10 of the Code of Federal Regulations, Part 72. The SNF is stored in dry cask storage systems, which most commonly consist of a welded austenitic stainless steel canister within a larger concrete vault or overpack vented to the external atmosphere to allow airflow for cooling. Some ISFSIs are located in marine environments where there may be high concentrations of airborne chloride salts. If salts were to deposit on the canisters via the external vents, a chloride-rich brine could form by deliquescence. Austenitic stainless steels are susceptible to chloride-induced stress corrosion cracking (SCC), particularly in the presence of residual tensile stresses from welding or other fabrication processes. SCC could allow helium to leak out of a canister if the wall is breached or otherwise compromise its structural integrity. There is currently limited understanding of the conditions that will affect the SCC susceptibility of austenitic stainless steel exposed to marine salts. NRC previously conducted a scoping study of this phenomenon, reported in NUREG/CR-7030 in 2010. Given apparent conservatisms and limitations in this study, NRC has sponsored a follow-on research program to more systematically investigate various factors that may affect SCC including temperature, humidity, salt concentration, and stress level. The activities within this research program include: (1) measurement of relative humidity (RH) for deliquescence of sea salt, (2) SCC testing within the range of natural absolute humidity, (3) SCC testing at elevated temperatures, (4) SCC testing at high humidity conditions, and (5) SCC testing with various applied stresses. Results to date indicate that the deliquescence RH for sea salt is close to that of MgCl{sub 2} pure salt. SCC is observed between 35 and 80 deg. C when the ambient (RH) is close to or higher than this level, even for a low surface salt concentration. (authors)

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DOE OSTI2015

Developing generic design alternatives for dry storage of used nuclear fuel at an interim storage facility - 15480

The Department of Energy (DOE) is beginning to lay the groundwork for implementing interim storage of used nuclear fuel (UNF) as recommended by the Blue Ribbon Commission on America's Nuclear Future in their report to the Secretary of Energy published on January 26, 2012. These plans include activities to 1) establish one or more Interim Storage Facilities (ISF) using consent-based siting, and 2) prepare for large-scale transport of UNF. The Administration released its Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (Strategy) on January 11, 2013. The Strategy includes a phased, adaptive, and consent-based approach to siting and implementing a comprehensive management and disposal system. The Strategy calls for an operational Pilot ISF by 2021, a Larger ISF by 2025, and a geological repository by 2048. The DOE Nuclear Fuels Storage and Transportation Planning Project (NFST) prepared a report in April 2013 titled, -A Project Concept for Nuclear Fuels Storage and Transportation.- This report developed the functions and requirements necessary for development of a Pilot and Larger ISF to meet the framework outlined in the Strategy as follows: - The UNF inventory is limited for the Pilot and Larger ISF as described in the Strategy. - It is assumed that bare fuel will be received in reusable transportation casks in significant quantities for the larger ISF and will not be solely limited to the receipt of fuel in dry storage canister (DSC) as is the Pilot ISF. This assumption was made because the method for accepting UNF from the utilities once the larger ISF begins operating has not yet been decided. - UNF storage alternative concepts identified in previous reports must be more fully developed to support alternative analysis. The purpose of this topic is to report on the development of the generic design alternatives that have been evaluated for the receipt and storage of the UNF at the initial Pilot ISF and Larger ISF. The generic design alternatives have been developed over the past few months by collaboration between the DOE and industry experts experienced in UNF facilities. The design alternatives will enable volunteer host communities to investigate generic design alternatives that could be fully developed for a site-specific location based on their unique design requirements. The design alternatives provide flexibility for additional capabilities to be developed and executed in a modular fashion such that expansion from a Pilot ISF to a Larger ISF could be achieved in an orderly manner. (authors)

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DOE OSTI2016

Innovative Solutions for Loading Smaller Standardized Dry Storage Canister Systems for Used Nuclear Fuel - 16232

An integrated team lead by EnergySolutions has developed and evaluated design concepts and loading processes for standardized transportation, aging and disposal (STAD) canister systems for the dry storage of United States (US) commercial used nuclear fuel (UNF). These STADs would be smaller than the Dual Purpose Canisters (DPCs) currently in use for storage and transportation of UNF at the nuclear power plant (NPP) sites in the US, so it was necessary to study the operational requirements and impacts related to their implementation at the NPPs and develop innovative approaches to mitigate these impacts. This work was funded by the US Department of Energy (DOE) to support the DOE in evaluating the option of using standardized canister systems for storage, transport, and disposal of US commercial UNF as part of an integrated waste management system. The NPP utilities are currently placing UNF into increasingly large DPCs because this reduces loading times and associated worker dose uptake. However, whether large DPCs may be able to be directly disposed is not known at this time, and will depend in part on future geologic disposal concepts and the DPC heat content. The use of STAD canisters rather than DPCs at the NPP sites and/or at an interim storage facility could avoid a potential need to repackage the UNF for disposal but, to make STAD canisters attractive for use, ways need to be found to fill and seal them efficiently from an operational perspective. This paper describes the generic design for a small STAD canister system, the loading processes and process improvements that were identified for the small, medium and large STAD canister sizes, the methodology for, and results from, the assessment of the performance of the loading processes, and the practicality of the results versus NPP operating experience. The work that this paper reports thus reflects research and development efforts to explore technical concepts that could support future decision-making by DOE. (authors)

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DOE OSTI2016

A Study on the Temperature Correlation between a Surface of Dry Storage Canister and Spent Fuel Clad - 16446

Analysis of temperature correlation between dry canister surface and spent fuel cladding is performed in this study. The result shows that the spent fuel cladding temperature is possibly estimated using canister surface temperature in normal condition and the result of estimation is depended on analysis model. Two analysis models are designed by using a hypothetical spent fuel model and thermal analysis for the models is performed by using CFX(v11.0) code. (authors)

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DOE OSTI2018

Systems and Tools to Facilitate Aging Management Inspections of Used Nuclear Fuel Dry Storage Systems - 18382

The Used Nuclear Fuel (UNF) dry storage systems (DSSs) are currently used at almost all the nuclear plants in the USA for the storage of their UNF as the spent fuel pools are running out of capacity to store any additional discharged fuel. Even though these DSSs are supposed to be at the reactor site for a short amount of time, they are expected to be at the reactor sites for an extended duration due to the unavailability of Interim Storage Facilities (ISF) or a permanent disposal sites like Yucca Mountain. Maintaining the integrity of the DSS canisters and storage overpacks so they can safely protect the fuel and maintain the integrity of UNF is of utmost importance during storage at reactor site ISFSI or at the ISF. Comprehensive and robust Aging Management Program (AMP) is an important aspect for DSSs to satisfy these requirements. In order to address this industry need, TN Americas have developed an enhanced NUHOMS{sup R} DSS licensed by NRC under 10 CFR Part 72 regulations and a comprehensive AMP development which includes prevention, inspection, monitoring and mitigation of any corrosion or degradation of DSS components. For DSC and HSM inspection, two remotely operating delivery systems have been developed using non-destructive examination (NDE) methods including robotic crawler and inspection ring system. This paper describes details of these developments and status of their deployment for implementation at various utility ISFSI sites. TN Americas completed the detailed design of the DSC inspection system and conducted functional tests of the inspection system on a DSC mockup and the system is ready for deployment at any NUHOMS{sup R} ISFSI site. TN Americas is committed to offer the most robust and comprehensive AMP systems, tools and services to the industry to assure the safety of the deployed DSS at the utility sites. (authors)

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DOE OSTI2018

Aging Management Considerations for Dry Cask Storage Canisters - 18472

Dry cask storage systems (DCSSs) are used to store used nuclear fuel (UNF) at independent spent fuel storage installations (ISFSIs) prior to final geologic storage or reprocessing. As storage durations increase beyond the twenty-year period commonly implemented for licensing the storage sites, it is important to consider aging related degradation issues for DCSS components. A large portion of the DCSS designs used throughout the world employ a ventilated concrete overpack with a welded stainless steel canister that confines the UNF. This paper explores key issues related to aging management for these canister components, including: (1) canister environment, (2) inspection limitations, and (3) aging management program guidance and requirements. While the austenitic stainless steel used for the canisters are generally resistant to most forms of environmental attack, it is possible for conditions to arise that lead to pitting and even stress corrosion cracking of the canister systems. A large number of studies related to canister degradation have been performed by industry groups and government researchers, both in the US and worldwide. These advances in the collective knowledge provide insight into risk factors for DCSS. Such information is beneficial to improve ISFSI siting decisions and ensure successful relicensing of existing ISFSIs. This paper highlights relevant research and also discusses applicability to degradation of other equipment and containers used to process and isolate UNF and other nuclear waste streams from the public and the environment. Inspection of the canister surface is an important tool to investigate and evaluate the potential for degradation. Existing DCSS designs typically do not offer ready access to the canister surface in order to perform the inspection. Further complicating inspection efforts are the surface conditions present on the sheltered canisters after extended storage times, including atmospheric debris such as dust and pollen. Given ongoing development efforts, inspection capabilities and associated limitations should be assessed at multiple points in time over the course of an aging management program to incorporate new advances in the field. This paper explores the limitations of currently available capabilities in inspection and delivery, and provides insight into the gaps remaining to be filled to permit an effective inspection program. Recommendations and requirements related to programs for aging management of canisters have been published or are in progress from a variety of groups, including industry groups, regulatory authorities, and Codes and Standards. An effective aging management program should consider the technical bases of these various inputs and maintain compliance with requirements. Given multiple sources, decisions will be required when considering conflicting guidance, and this paper will include discussion of the relative merits of the various approaches. (author)

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DOE OSTI2019

Corrosion Monitoring in an Irradiated/Used Fuel Dry Storage Container - 19193

A corrosion monitoring system was developed to monitor the corrosion behaviour of steel components embedded in the high density concrete of a Dry Storage Container (DSC). The DSC is a free-standing reinforced concrete container, with an inner carbon-steel liner and an outer carbon-steel shell, for the storage, on-site transfer and off-site transportation of irradiated Candu fuel. Normally, uncontaminated concrete is benign with regards to embedded steel components because high alkalinity in the concrete leads to formation of a passive film on the steel surface, which prevents excessive metal loss. However, corrosion of steel in concrete may be promoted by one or more of local concentration of chloride ions or local loss of alkalinity. For the DSC, it is recognized that the above mechanism(s) are unlikely, however, if any did exist, the corrosion mechanisms that could then occur would include corrosion of carbon steel components and stress corrosion cracking of 304L stainless steel components. In order to confirm that these unlikely events are not occurring, Ontario Power Generation has undertaken a project to investigate the corrosion behaviour of metallic components embedded in the DSC's high density concrete. A corrosion monitoring system that can be installed within the concrete space of a DSC was designed and installed to monitor changes in temperature, corrosion potential, corrosion rate, and electrochemical noise. The corrosion monitoring system was commissioned in July 2012, followed by the commencement of monitoring and measurements. The corrosion data, collected for the three years from year 2012 to 2015, were analyzed. It was concluded that the corrosion rates of both carbon steel and stainless steel within the DSC are very low and consistent with the intended minimum operational life of the DSC. The monitoring system as a whole has allowed a systematic and long term judgement regarding the conditions within the DSCs. (authors)

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DOE OSTI2020

Optimization of Dry Storage Canister Cutting Operations - 20534

A recent project investigated the optimal cutting method for the opening of a welded dry storage/shielded canister (DSC) or dual purpose canister (DPC) containing Used Nuclear Fuel (UNF). Due to the lack of a disposal path for UNF in the U.S., the majority of UNF is currently moved into welded DSCs and DPCs designed by Orano TN, NAC, and Holtec. As the DSCs/DPCs were neither designed nor licensed for disposal and may not be able to be emplaced in a geologic repository due to physical emplacement constraints, near-term thermal limitations, or long-term criticality issues, the UNF in these existing DSCs/DPCs may need to be repackaged into transportation, aging, and disposal canisters (TADs), generic standard TADs (STADs), transportation casks, new cask/canister systems, and/or cask/canister/package systems suitable for disposal. These DSCs/DPCs may also be opened to simply remove the UNF in preparation for recycling, re-storage, or placement into a waste package suitable for disposal. Regardless of need, the DSCs/DPCs would require to be cut open by a potentially large scale operation. This project examined the multiple means for cutting welded metal systems and considered several factors to determine an optimal approach. Issues arose around some of the cutting approaches when applied to systems with 2 or 3 lids and with pre-cutting gas testing required. The resulting preferences in cutting methods with an optimized application for the opening of DSCs/DPCs are presented. (authors)

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DOE OSTI2016

A Scintillation-Fiber Based Cosmic-ray Muon Tomography System for Imaging Dry Storage Cask

Because of the growth of the nuclear power industry in the United States and the policy decision to ban reprocessing of commercial spent nuclear fuel, the spent fuel inventory at commercial reactor sites has been increasing. Spent nuclear fuel presents extra complexity of security and proliferation issues. These fuel assemblies are practically inaccessible for inspection purposes, as reopening a DSC would require special facilities and would be tremendously expensive. Cosmic-ray muon Tomography has been studied in the past for various applications and was demonstrated to be a good non-destructive assay technique for high-Z materials, such as spent nuclear fuel assemblies in dry storage casks (DSC). Compared to conventional imaging techniques, muon imaging has some advantages due to its negligible health risk and high penetrating power. In this paper, we report our simulation study on imaging a DSC using muon Tomography technique. The Point of Closest Approach (POCA) and the Maximum-Likelihood Expectation- Maximization (ML-EM) algorithms are implemented and evaluated. A scaled-down prototype muon tomography system is proposed and studied. (authors)

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