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At least 469 records · Page 26
All sourcesNASA NTRSDOE OSTI
NASA NTRS2022

An Overview of Contamination Control for the James Webb Space Telescope Launch Campaign

The James Webb Space Telescope (JWST) is a large, infrared space telescope operating at Lagrange point 2. JWST is a joint effort between NASA, ESA, and CSA and was launched from the Centre Spatial Guyanais (CSG) on an Ariane 5 rocket in December 2021. The three-month launch campaign utilized enhanced contamination controls to meet JWST’s strict cleanliness requirements. Prior to launch, JWST was permitted to only be exposed to ISO Class 7 cleanrooms, whereas the processing facilities at CSG are ISO Class 8. NASA, ESA, Arianespace, and CNES implemented temporary upgrades to the nominal contamination control operations for the launch campaign unique to JWST, including the use of vetted, portable High Efficiency Particulate Air (HEPA) filter walls, pre-entrance cleanliness acceptance surveys of each facility and the intra-plant transporter, tightened cleanroom protocols, upgraded garmenting and laundering techniques, cleaning of Self-Contained Atmospheric Protection Ensemble (SCAPE) suits, increased maintenance, staffed pre-cleaning stations, adaptation of the house purge network, and a contamination control enclosure atop the Ariane 5 launcher prior to fairing encapsulation. The Ariane 5 fairing interior and Vehicle Equipment Bay membrane also received multiple cleanings, detailed inspections, and verification sampling to achieve necessary cleanliness levels. The fairing itself was specially sealed to protect the inner environment with just a small, door porthole accessible via diving board for final closeout of the purge interface. All of these enhancements together allowed JWST to meet its contamination requirements for launch, ensuring successful post-separation deployments and mission science.

Contamination Control↗
NASA NTRSDate not supplied

Development of a Microlith® Catalytic Oxidizer for Exploration Trace Contaminant Control

The state-of-the-art in long mission duration spacecraft trace contaminant control processes rely on high-temperature catalytic oxidation for light contaminant removal. Target compounds for oxidation include metabolic methane, carbon monoxide, and low molecular weight volatile organics such as formaldehyde and methanol. Precision Combustion, Inc. and NASA Marshall Space Flight Center have been developing and testing prototype high temperature catalytic oxidizers based on PCI’s patented Microlith® technology to meet the requirements of future spaceflight exploration missions. To this end, our latest generation Microlith oxidizer, featuring an integrated heat recuperator, was subjected to endurance testing to simulate catalyst ageing over a Mars transit mission duration. Periodic reactor health testing indicates our approach results in a robust contaminant control solution for exploration missions beyond low earth orbit. Based on the demonstrated performance of this unit, a next-generation prototype was designed to meet exploration contaminant load control demands while upgrading the prototype form and fit to match flight-compatible interfaces. Prototype design considerations intended to reduce power consumption, impacting process thermal and hydraulic performance, are discussed herein.

Trace Contaminant Control↗
NASA NTRSDate not supplied

Overview of Contamination Control for the James Webb Space Telescope Launch Campaign

The James Webb Space Telescope (JWST) is a large, infrared space telescope operating at Lagrange point 2. JWST is a joint effort between NASA, ESA, and CSA and was launched from the Centre Spatial Guyanais (CSG) on an Ariane 5 rocket in December 2021. The three-month launch campaign utilized enhanced contamination controls to meet JWST’s strict cleanliness requirements. Prior to launch, JWST was permitted to only be exposed to ISO Class 7 cleanrooms, whereas the processing facilities at CSG are ISO Class 8. NASA, ESA, Arianespace, and CNES implemented temporary upgrades to the nominal contamination control operations for the launch campaign unique to JWST, including the use of vetted, portable High Efficiency Particulate Air (HEPA) filter walls, pre-entrance cleanliness acceptance surveys of each facility and the intra-plant transporter, tightened cleanroom protocols, upgraded garmenting and laundering techniques, cleaning of Self-Contained Atmospheric Protection Ensemble (SCAPE) suits, increased maintenance, staffed pre-cleaning stations, adaptation of the house purge network, and a contamination control enclosure atop the Ariane 5 launcher prior to fairing encapsulation. The Ariane 5 fairing interior and Vehicle Equipment Bay membrane also received multiple cleanings, detailed inspections, and verification sampling to achieve necessary cleanliness levels. The fairing itself was specially sealed to protect the inner environment with just a small, doored porthole accessible via diving board for final closeout of the purge interface. All these enhancements together allowed JWST to meet its contamination requirements for launch, ensuring successful post-separation deployments and mission science.

James Webb Space Telescope↗
NASA NTRS2022

Overview of Contamination Control for the James Webb Space Telescope Launch Campaign

The James Webb Space Telescope (JWST) is a large, infrared space telescope operating at Lagrange point 2. JWST is a joint effort between NASA, ESA, and CSA and was launched from the Centre Spatial Guyanais (CSG) on an Ariane 5 rocket in December 2021. The three-month launch campaign utilized enhanced contamination controls to meet JWST’s strict cleanliness requirements. Prior to launch, JWST was permitted to only be exposed to ISO Class 7 cleanrooms, whereas the processing facilities at CSG are ISO Class 8. NASA, ESA, Arianespace, and CNES implemented temporary upgrades to the nominal contamination control operations for the launch campaign unique to JWST, including the use of vetted, portable High Efficiency Particulate Air (HEPA) filter walls, pre-entrance cleanliness acceptance surveys of each facility and the intra-plant transporter, tightened cleanroom protocols, upgraded garmenting and laundering techniques, cleaning of Self-Contained Atmospheric Protection Ensemble (SCAPE) suits, increased maintenance, staffed pre-cleaning stations, adaptation of the house purge network, and a contamination control enclosure atop the Ariane 5 launcher prior to fairing encapsulation. The Ariane 5 fairing interior and Vehicle Equipment Bay membrane also received multiple cleanings, detailed inspections, and verification sampling to achieve necessary cleanliness levels. The fairing itself was specially sealed to protect the inner environment with just a small, doored porthole accessible via diving board for final closeout of the purge interface. All these enhancements together allowed JWST to meet its contamination requirements for launch, ensuring successful post-separation deployments and mission science.

James Webb Space Telescope, launch, contamination,↗
DOE OSTI2017

Innovative Data Management System in Support of Remedial Actions for Legacy Radioactive Contamination - 17280

The Port Hope Area Initiative (PHAI) is a project mandated and funded by the Government of Canada to remove contamination from properties with legacy low-level radioactive waste (LLRW) contamination arising from a crown-owned radium and, later, uranium refinery in the Town of Port Hope, Ontario. From 1976 to 1981, a community clean-up project was undertaken, with the specific purpose to decrease the level of historic LLRW contamination within Port Hope. Since then, residual LLRW has been managed by the Low Level Radioactive Waste Management Office (LLRWMO) (and its predecessors). The PHAI and the Port Hope Project (PHP) were initiated in 2001 with a formal agreement between affected municipalities and the federal government to develop a safe, long-term management solution for the historic LLRW remaining within Port Hope. An important activity of the PHP is the survey of about 4,800 'small scale sites' (SSS) throughout the community to confirm the presence or absence of LLRW. This involves surveys of properties based on the measurement of exterior gamma, contaminated objects and surfaces, soil concentrations and indoor radon and classification to Port Hope project specific criteria. A very large amount of information is involved in the project including; scheduling individual field visits to the properties, capture of field data and comments, laboratory sample tracking, QA/QC, report generation and internal and client project reporting at regular schedules. Field data collection of exterior gamma radiation surveys includes direct (real time) and interactive loading of data into the Information Management (IM) system to support initial QA/QC and reporting back to the field on radiation levels. Screening soil measurements including X-ray fluorescence (XRF) and gamma radiation are collected from all 20 cm increments in each borehole in addition to down-hole gamma radiation measurements and logging of soil characteristics which are used in documentation and interpretation of the property condition. The IM system outlined in this paper was developed to respond to the requirements for radiological surveys in Port Hope. The IM system continues to evolve as a part of continuing review and improvement. The IM system incorporates Web-enabled field tools and cloud hosted data and applications, provides increased field efficiency, timeliness in reporting, real time QA/QC analysis, and consistency in tracking project advances and changes made to the data for decision-making and reporting on an ongoing basis. Examples of specific applications are provided. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

EPRI Report: Review of Geostatistical Approaches to Characterization of Subsurface Contamination - 17442

The key metric in the final release of a nuclear facility from radiological controls following plant decommissioning is the potential long-term radiation exposure to future users of the site. This is estimated from modeling of the exposure that could conceivably result from residual contamination remaining on the site in buildings, soil and groundwater after the completion of decontamination, dismantlement and remediation activities. A key input to such modelling is characterization data obtained from surveys and sampling. To date, the regulatory guidance for conducting the final status survey required to show compliance with regulator approved site release limits (i.e., radionuclide concentrations or contamination levels) has been limited to surface contamination. EPRI has completed a project that provides guidance for use of geo-statistics in the development of a site final status survey that will address the impact of dose to a future user of the site from subsurface contamination. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Observation Technology for Remote Operation in Contaminated Turbid Water - 16113

Remote underwater work in contaminated tanks and pools is one of major decontamination and decommissioning works under high-dose radiation environment. Generally, in this kind of work, visual information obtained by a camera (an optical camera) is limited due to turbid water caused by suspended sludge particles in the water and it makes remote underwater work difficult to be performed safely and efficiently. Therefore, some alternative observation methods to optical cameras have been required. In order to satisfy this requirement, the alternative observation technology which can obtain visual information in contaminated turbid water has been developed since 2014. It is a technology using an acoustic imaging system in a designated airtight container. It provides the visual information in real time regardless of turbidity without significant contamination of any parts of the system. Also, it is able to provide the location information of underwater objects with contactless. This paper will present development details of this innovative observation technology and its effectiveness to various remote works in contaminated turbid water. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Size Reduction of Contaminated Magnox Pond Skips Using Laser Cutting - 16192

Magnox and TWI Ltd (TWI) have recently developed a first-of-a-kind automated remote laser cutting facility. The facility has been commissioned at Hinkley Point 'A' (HPA) nuclear power station and used to successfully demonstrate the capability of TWI's laser cutting technology to remotely size reduce contaminated Intermediate Level Waste (ILW) Magnox pond skips. The benefits of the facility include reduced cutting times, significantly reduced dose uptake, and significant cost savings. The facility has been designed with a 'plug-and-play' approach such that it could be de-planted and re-mobilised to another nuclear site for other applications. Three contaminated ILW Magnox pond skips with activities of 10.3, 25.1 and 218 GBq/t have been successfully size reduced with this facility; with less than 2.5 hours required to size reduce one skip, and the elapsed laser cutting time being less than 40 minutes. Subsequent radiological assessment showed that the surface contamination and airborne activity were confined within a specifically designed modular containment unit. Continuous real-time air monitoring results indicated a rapid rise and fall of airborne activity. The largest proportion of the airborne activity was removed from the modular containment within 10 minutes by local HEPA ventilation, with the residual activity taking approximately one hour to settle out entirely. The measured dose uptakes were mostly associated with manual handling of the skips to and from the size reduction facility, thus indicating the significance of an automated remote skip size reduction facility. This paper describes the design and performance of the laser skip size reduction facility and presents results of the radiological assessment for three contaminated skips with varying activities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Estimating Radionuclide Activity in Surface Contamination for GTCC Activated Metal Waste Streams - 18236

The U.S. Nuclear Regulatory Commission's licensing requirements for land disposal of low-level radioactive waste (LLRW) in 10 CFR Part 61 classify LLRW wastes as Class A, B, C, or Greater-Than- Class C (GTCC). GTCC waste includes activated metals that are generated primarily by nuclear power reactors. Activated metals represent a significant volume (880 cubic meters) of GTCC wastes that may be generated as current commercial power reactors are decommissioned. Additionally, these wastes are expected to contain radionuclides that are very long-lived and are mobile in the environment (e.g., Tc-99 and I-129) as well as transuranic radionuclides that, while not as mobile as other radionuclides, have greater potential for health consequences should such radionuclides reach receptor locations in sufficient concentrations. Quantities of surface contamination on activated metals have typically been reported using a combination of assumptions, calculations, and measurements. For example, projections of future activity associated with surface contamination, or the surface activity, for the activated metals is dependent on assumptions made regarding fuel behavior (e.g., modern fuel performance is expected to be different from fuel performance in the 1970's). In this study, we examined published information to better understand how assumptions, calculations, and measurements used for estimating quantities of surface contamination on activated metals can influence the estimated quantities. The analysis in this report was performed to better understand how estimates for the activated metal inventory of GTCC metal could influence potential decisions regarding the siting and design of disposal facilities. It was found that the variability in surface contamination either measured or estimated was sufficiently large that characterization of the radionuclide inventory for GTCC activated metals, especially the transuranic radionuclides, is critically important for establishing the siting and design requirements for a disposal facility. Overly conservative assumptions for the inventory could significantly limit disposal options, whereas, overly optimistic assumptions with respect to the inventory could lead to a disposal facility that may not protect off-site receptors. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Laser-Induced Breakdown Spectroscopy for Contamination Detection in Concrete on Nuclear Facilities - 18296

Laser-Induced Breakdown Spectroscopy (LIBS) provides a real-time analytical technique for determining the elemental composition of a sample. This work was carried out to determine the suitability of the method for contamination detection in concrete. Cement paste samples were cast, containing simulant radionuclide contaminant salts of Co and Ni at 0.1 wt% inclusion. LIBS was then carried out on the samples, and contaminated samples compared to an uncontaminated ordinary portland cement (OPC) reference. A ratio of normalised peak intensities was used to determine differences in spectra between the samples. Where differences between sample and reference spectra were discovered, the National Institute of Standards and Technology spectral lines database was consulted, the identity of the contaminants could be confirmed, and Co and Ni were both identified at less than 0.1 wt% inclusion. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

In Situ Monitoring of Groundwater Contamination for Sustainable Remediation Using the Kalman Filter - 18423

Groundwater monitoring is critical for nuclear-related facilities as well as radioactively contaminated sites. Recent advances in sensing, data analytics and simulation capabilities provide substantial opportunities to improve and change current monitoring procedures. In particular, we need a paradigm shift from contaminant-only or compliance-only monitoring programs to comprehensive monitoring, i.e., including other ancillary environmental variables for a holistic understanding of the groundwater systems and plume behaviors. Such new approaches are needed for the effective implementation of sustainable remediation (enhanced and natural attenuation), and they have great potential for cost reduction in site monitoring. This paper reviews recent developments for improving long-term monitoring, with focus on the effective use of in situ sensors, data analytics and simulation capabilities. In particular, we highlight a recent application of the Kalman filter algorithm to estimate contaminant concentrations continuously in real time, based on in-situ measured water quality parameters (e.g. electrical conductance and pH) and sparse groundwater sampling. The results show that we can reduce the groundwater sampling frequency significantly, while capturing the dynamics of short- and long-term contaminant concentration changes. Such advanced and integrated monitoring systems will be beneficial for local residents (e.g., to ensure the safety by detecting adverse events early, enabling a swift response) as well as for site operators (e.g., to gain/improve public acceptance, to be better prepared for litigations and false claims, and to reduce overall monitoring cost). (authors)

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

Rehabilitation of Westbay{sup R} Wells with PCE-Contaminated Tubing Fluid - 19250

In November 2015, tetrachloroethylene, also known as PCE, was discovered in groundwater samples collected from a Westbay{sup R} multi-level groundwater monitoring well at the Idaho National Laboratory (INL).a The result was unexpected due to the remote location of the well. Subsequent investigation determined that PCE was not present in the groundwater. The detected PCE was due to inadvertent contamination of the tubing fluid in the Westbay well-monitoring system. Further investigation showed that three of the 11 Westbay wells at the INL contained PCE-contaminated tubing fluid at concentrations above the U.S. Environmental Protection Agency maximum contamination level (5 μg/L); the three wells were identified for rehabilitation as part of the INL well maintenance program. Well rehabilitation would either remove and replace the PCE-contaminated tubing fluid or remove the PCE from the tubing fluid. The interior of the Westbay well casing is isolated from the surrounding groundwater and filled with tubing fluid (either distilled or potable water). Groundwater samples are collected by opening sealed ports using a specialized sampling device. The unique construction prevents the direct interaction of the groundwater and tubing fluid. The tubing fluid also supports the structural integrity of the Westbay wells. The unique construction of the Westbay wells-i.e., the small diameter (5.08 cm [2 in.]) and the depths of the tubing fluid ranging from 144.8 to 419 m (475 to 1,376 ft) below ground surface-posed unique challenges to the rehabilitation. Because the tubing fluid provides structural integrity to the Westbay well, the fluid cannot be removed and then replaced without damaging the integrity of the Westbay well. Additionally, the small diameter of the systems and the associated depths limit the availability of equipment that can be used for the rehabilitation. After an evaluation of potential methods, it was determined that the use of an in-well, granular-activated-carbon filtration swab deployed via a wire line would provide the safest and most cost-effective method for rehabilitation. Rehabilitation commenced during the summer of 2018 and is ongoing with measurable success. (authors)

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

PlumeSeeker{sup TM}: A Model-Based Least-Cost Monitoring Network Design Technology for 3-D Contaminant Plume Boundary Delineation - 19582

Delineating the extent of contamination in an aquifer is a pre-requisite for designing remediation schemes as well as for satisfying regulators and stakeholders. Contaminant plumes are typically delineated using either monitoring well locations with observed concentrations below remedial goals or with computer-drawn contour maps based on available concentration measurements in the groundwater. Computer-generated plume information lacks ground truth resulting in uncertainty about the true limits of contamination. The location of groundwater delineation wells is usually chosen solely based on professional judgement and experience. Both approaches can be inefficient, risky and often unnecessarily expensive. PlumeSeeker{sup TM} is a software-based technology well-suited for the optimal delineation of radiological or emerging contaminant plumes with single or multiple source locations. The software is an enhancement of a university research code for plume delineation using geostatistical and stochastic modeling tools integrated with the widely used groundwater flow and transport modeling software MODFLOW-SURFACT{sup TM}. PlumeSeeker{sup TM} increases the overall confidence in the location and geometry of the plume boundary through the sequential (i.e. a rank-ordered listing) or batch (i.e. a suite of multiple wells) selection of existing or new monitoring wells based on the criteria of maximizing plume boundary uncertainty reduction and on new field information. Using PlumeSeeker{sup TM}, remediation managers can optimally locate new wells at sites where well installation costs are high or hydrogeology is complex. Applicable at sites with or without existing monitoring wells, PlumeSeeker{sup TM} is particularly powerful for optimally allocating project resources (labor, well installation, and laboratory costs) between existing wells and sampling at new locations. An application of PlumeSeeker{sup TM} at a DoD installation demonstrates how the cost of delineating a plume can be minimized. (authors)

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

Engineering Controls for the Processing and Repackaging of Gloveboxes Contaminated with Plutonium - 19629

Gloveboxes used for processing plutonium (Pu)-238 at the US DOE Mound site in Miamisburg, Ohio, in support of the United States space mission were packaged in non-standard waste boxes and sent to the INL Site for temporary disposal. In addition to the gloveboxes, an assortment of smaller items, all with varying levels of Pu-238 contamination, were found in the non-standard waste boxes. The characteristics of Pu-238 make it especially difficult to contain and control contamination; alpha recoil phenomena and nanometer particle sizes lend to the contamination exhibiting near gas like characteristics. The Idaho Cleanup Project Core contractor, Fluor Idaho, LLC, engineered and deployed a waste processing containment with specialized ventilation and processes to characterize and disposition this waste. This paper summarizes the successes and lessons learned from processing Pu-238-contaminated waste. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

The Nature and State of Groundwater Contamination at the Nevada National Security Site: What Have We Learned from Decades of Groundwater Analysis? - 20337

The regulatory framework for remediating radionuclide contamination from underground nuclear testing at the Nevada National Security Site (NNSS) is based on a combination of characterization and modeling studies, monitoring, and institutional controls [1]. Currently, tritium is the largest contributor (∼90%) to the estimated 44.6 million-curie radionuclide inventory resulting from underground testing [2]. Because of its short half-life (12.32 years), its relative contribution reduces below 10% of the total radiologic inventory over the next 120 years as a result of radioactive decay. Although tritium levels are observed well above the Safe Drinking Water Act (SDWA) maximum contaminant levels (MCLs) in groundwater, other radionuclides are well below their MCLs except within the nuclear test near-field (nuclear test cavity and chimney) environment. In fact, most device-derived radionuclides are below their MCL in groundwater even in samples collected from this near-field environment. The distribution of radionuclides following the nuclear detonation greatly influences the availability of potential contaminants for groundwater transport. Tritium is initially distributed in the gas phase, later as tritiated water in steam, and finally as liquid water, and is available to groundwater transport away from the near-field environment. Other radionuclides that are mobile in groundwater are {sup 14}C, {sup 36}Cl, {sup 99}Tc, and {sup 129}I though their radiologic inventory is small when compared to tritium. Many radionuclides (e.g. U, Pu, Am) are incorporated to a significant extent into the melt glass at the bottom of the cavity and are accessible to groundwater primarily through the slow process of glass dissolution. These radionuclides are also adsorbed to the surfaces of the crushed rock within the cavity and chimney which limits their migration in groundwater. Although colloid facilitated transport of radionuclides at the NNSS has been observed [3], radionuclide concentrations decrease with time and migration distances due to desorption and colloid filtration processes. Current studies indicate that radionuclides associated with colloids are unlikely to migrate downgradient from NNSS underground nuclear tests at concentrations above the SDWA MCL [4][5]. The results of over 50 years of sampling, along with an understanding of these post detonation processes, indicate that tritium is the only contaminant of concern downgradient of testing and that even tritium will not exceed its MCL in groundwater after ∼120 years. Although other longer-lived radionuclides may continue to be released slowly from the near-field environment they will likely never reach levels exceeding their MCLs in groundwater downgradient of the NNSS. Groundwater monitoring will continue to verify these observations. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
NASA NTRS1996

Spacecraft Maximum Allowable Concentrations for Selected Airborne Contaminants

The National Aeronautics and Space Administration (NASA) has developed spacecraft maximum allowable concentrations (SMACs) for contaminants that might be found in the atmosphere within spacecraft during space missions to ensure the health and well-being of astronauts traveling and working in this unique environment. In volume 1 of this series, NASA developed SMACs for 11 compounds: acetaldehyde, ammonia, carbon monoxide, formaldehyde, Freon 113, hydrogen, methane, methanol, octamethyltrisiloxane, trimethylsilanol, and vinyl chloride. Volume 2 includes SMACs for 12 more airborne contaminants: acrolein, benzene, carbon dioxide, 2-ethoxyethanol, hydrazine, indole, mercury, methylene chloride, methyl ethyl ketone, nitromethane, 2-propoanol, and toluene. In developing SMACs from the toxicological literature, NASA followed the Guidelines for Developing Spacecraft Maximum Allowable Concentrations for Space Station Contaminants published in 1992 by the National Research Council.

Spacecraft contamination↗
DOE OSTI2015

Parameter estimation and prediction for groundwater contamination based on measure theory

The problem of groundwater contamination in an aquifer is one with many uncertainties. Properly quantifying these uncertainties is es- sential in order to make reliable probabilistic based predictions and decisions regarding remediation strategies. In this work, a measure-theoretic frame- work is employed to quantify uncertainties in a simpli ed groundwater con- tamination transport model. Given uncertain data from observation wells, the stochastic inverse problem is solved numerically to obtain a probability measure on the space of unknown model parameters characterizing ground- water ow and contaminant transport in an aquifer, as well as unknown model boundary or source terms such as the contaminant source release into the environment. This probability measure is used to make predictions of future contaminant concentrations and to analyze possible remediation techniques. The ability to identify regions of small but nonzero probability using this method is illustrated.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2025

Contaminant Investigation and Pre‐Processing Opportunities for Textile‐To‐Textile Recycling

Millions of metric tons of textiles are landfilled or incinerated each year in the United States, with less than 1% of textiles recycled into new clothing or fabrics. To counter this trend, a growing number of companies and researchers are exploring how a circular economy can be applied to support textile‐to‐textile recycling. A significant barrier they face comes down to quickly and efficiently extracting pure feedstock material from post‐consumer garments that feature a mix of natural and synthetic fibers. Textile recyclers prefer pure feedstocks, as working with mixed sources typically means lower throughput, higher risk of equipment failure, and diminished business margins. To facilitate a circular economy for textiles, methods, and technologies are needed that can efficiently separate out materials and contaminants from end‐of‐life textiles to increase the flow of pure feedstocks to recyclers. This paper summarizes findings from interviews with a cross section of textile recyclers and from a review of literature to define basic feedstock requirements. In addition to our qualitative research, we deconstruct a bale of post‐consumer textiles and analyze them using computer‐vision imaging, Fourier transform infrared spectroscopy (FTIR), and machine learning. The resulting data are used to set system‐level design inputs for an automated contaminant removal system to process post‐consumer clothing into appropriate feedstocks for recycling. To set the system's levels for automated real‐time near‐infrared analysis, we identify the minimum percentage of primary material that any single garment in a load of used clothing must contain for the average of the full output stream to meet the target purity levels of recyclers. Here, the envisioned automated system can also address undesirable trace materials that might contaminate the processed stream by using imaging cameras coupled with artificial intelligence to identify sections of clothing for de‐trimming. Proof‐of‐concept machine learning algorithms are evaluated to locate and identify trims or garment areas with hidden contaminant materials. Integrating these methods into automated textile cutting systems can provide a cost‐effective means for increasing feedstock purity from used clothing, which can advance circularity for textiles by helping recyclers to reach production volumes and quality targets that were not possible solely with manual dismantling operations.

Parsons, Ryan [Rochester Institute of Technology, ↗