Paper #51: Multiple-Use of Unmanned Aircraft Systems for Improved Physical Security, Source Recovery, and Emergency Response.
Abstract not provided.
Potter, Michelle↗
SEARCH · Search NASA
Results for “Source Recovery”
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.
Unreviewed Disposal Question Evaluation: Disposal of the Off-Site Source Recovery Program Type-B Cask Shipments at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site, Nye County, Nevada
Explore the source record for details and available documents.
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Richard Hodes Memorial Award Lecture - Development and Certification of New Type-B Containers for the Recovery of High-Activity Sealed Sources - 18710
The US Department of Energy (DOE) National Nuclear Security Administration (NNSA) Off-Site Source Recovery Program (OSRP) has successfully completed a project to design, test, and certify two new Type-B transportation packages. Since about 2011 a shortage of these containers has significantly constrained the recovery and disposal of commercially licensed high activity radioactive sealed sources. These new packages will enable NNSA/OSRP to transport a majority of the high-activity Cs-137 and Co-60 devices encountered in the coming years and decades. The 435-B is an unshielded, leak-tight container, which can be used to ship common shielded devices, such as the teletherapy source drawers and irradiators that contain high-activity Co-60 and Cs-137 sources. The 380-B is a much larger, leak-tight, lead-shielded Type B cask capable of transport by truck, rail, ship, or air. Additionally, to encourage and facilitate the development of transportation capacity, DOE/NNSA intends to make the design documentation available at no cost to commercial vendors. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Utilization of the water soluable fraction of wheat straw as a plant nutrient source
Recovery of water soluble, inorganic nutrients from the inedible portion of wheat was found to be an effective means of recycling nutrients within hydroponic systems. Through aqueous extraction (leaching), 60 percent of the total inorganic nutrient weight was removed from wheat straw and roots, although the recovery of individual nutrients varied. Leaching also removed about 20 percent of the total organic carbon from the biomass. In terms of dry weight, the leachate was comprised of approximately 60 percent organic and 40 percent inorganic compounds. Direct use of wheat straw leachate in static hydroponic systems had an inhibitory effect on wheat growth, both in the presence and absence of microorganisms. Biological treatment of leachate either with a mixed microbial community or the oyster mushroom Pleurotus ostreatus L., prior to use in hydroponic solutions, significantly reduced both the organic content and the inhibitory effects of the leachate. The inhibitory effects of unprocessed leachate appear to be a result of rapidly acting phytotoxic compounds that are detoxified by microbial activity. Leaching holds considerable promise as a method for nutrient recycling in a Controlled Ecological Life Support System (CELSS).
Mackowiak, C. L.↗
The use of LiDAR and decision-making framework for recovery of high-activity radioactive sources
INL Virtual Walkdown for source recovery
99 - GENERAL AND MISCELLANEOUS↗
Sustainable Security through International Source Repatriation - 19659
Ensuring that there is a viable pathway for characterizing, transporting, and disposing of disused radioactive sealed sources (sources) is essential to any end-of-life management strategy. The Off-Site Source Recovery Program, sponsored by the Department of Energy National Nuclear Security Administration's Office of Radiological Security, provides permanent and sustained threat reduction through the secure removal and repatriation of disused sealed radioactive sources of United States origin at international locations. With over two decades of operations, the Off-Site Source Recovery Program has developed source removal processes and techniques to ensure the compliant, effective and timely disposition of the material. For device disassembly support, the program subcontracts vendors qualified and experienced in source extraction from devices. United States origin source repatriations provide for permanent threat reduction and reduce their overall global footprint. (author)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Los Alamos National Laboratory Release of Cesium-137 Corrective Action Plan
This Corrective Action Plan (CAP) was developed by a team chartered by John Sarrao, Deputy Director for Science, Technology, and Engineering (DDSTE), to review and respond to the findings of the Joint National Nuclear Security Administration/Triad National Security (NNSA/Triad) Investigation Team (JIT) Joint Investigation Report for the “Sealed Source Recovery at the University of Washington Harborview Training and Research Facility Results in Release of Cesium-137 on May 2, 2019,” dated March 30, 2020. On May 2, 2019, International Isotopes, Inc. (INIS), a subcontractor to Triad National Security, LLC, inadvertently breached a sealed cesium-137 source at the University of Washington (UW), Harborview Medical Center Research and Training (HRT) building in downtown Seattle while attempting to recover the source for the National Nuclear Security Administration (NNSA) Off-Site Source Recovery Program (OSRP). The source breach resulted in contamination of personnel and the HRT building, as well as a release of radioactive material to the environment
07 ISOTOPE AND RADIATION SOURCES↗
Evaluation of the Radioactive Material Released in the Harborview Research and Training Building and Some Implications for Emergency Response
On 2 May 2019, during the 137 Cs source recovery operation, a source capsule in a research irradiator containing approximately 77.1 TBq was breached. Based on a geometric reconstruction analysis of the damage to the capsule, approximately 46.3 GBq (0.04%) was impacted by the chop saw (grinder) inside a mobile hot cell on the loading dock at the University of Washington Harborview Research and Training (HRT) Building. A very small fraction of the material impacted, less than 1%, was released from the mobile hot cell and then to the rest of the HRT Building. The objectives of this project were to assess the accidental release of 137 CsCl and its implications related to emergency response methods and the ramifications of 137 CsCl transport. The phenomenology of this event was also compared with past alkali halide dispersal events. The vast number of measurements and samples collected by the remediation contractors, the Department of Energy’s Nuclear Emergency Support Team, and the small number of retrospective samples collected by the authors informed the analysis. The techniques included (1) autoradiography and electron microscopy of samples collected from the HRT Building and the irradiator, (2) 3D visualization of deposition on surfaces and within the ventilation system, and (3) a study of the damage to the source capsule to evaluate the Cs particle size and particle composition due to the grinding accident. Subsequently, the cesium contaminant transport through the numerous pathways in the building was reconstructed to assess the deposition on surfaces as a function of particle size. Furthermore, the implications for emergency response are relevant to data quality and management. A Data Quality Objective guides data collection methods so that they have appropriate accuracy and precision for the intended application. Recommendations were made with respect to the sample collection protocols and archiving of samples.
46 - INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AN↗
Evaluation of the Radioactive Material Release in the Harborview Research and Training Building and Implications for Emergency Response
On May 2, 2019, during the 137 Cs source recovery operation, a source capsule in a research irradiator containing approximately 77.1 TBq was breached. Based on a geometric reconstruction analysis of the damage to the capsule, approximately 46.3 GBq (0.04%) was impacted by the chop saw (grinder) inside a Mobile Hot Cell (MHC) on the loading dock at the University of Washington Harborview Research and Training (HRT) Building. A very small fraction of the material impacted, less than 1%) was released from the Mobile Hot Cell and then to the rest of the HRT Building. The objectives of this project were to assess the accidental release of 137 CsCl and its implications related to emergency response methods and the ramifications of 137 CsCl transport. The phenomenology of this event was also compared with past alkali halide dispersal events. The vast number of measurements and samples collected by the remediation contractors, the Department of Energy's Nuclear Emergency Support Team, and the small number of retrospective samples collected by the authors informed the analysis. The techniques included (1) autoradiography and electron microscopy of samples collected from the HRT Building and the irradiator, (2) 3D visualization of deposition on surfaces and within the ventilation system, and (3) a study of the damage to the source capsule to evaluate the Cs particle size and particle composition due to the grinding accident. Subsequently, the cesium contaminant transport through the numerous pathways in the building was reconstructed to assess the deposition on surfaces as a function of particle size. The implications for emergency response are relevant to data quality and management. A Data Quality Objective (DQO) guides data collection methods so that they have appropriate accuracy and precision for the intended application. Recommendations were made with respect to the sample collection protocols and sample archival.
61 RADIATION PROTECTION AND DOSIMETRY↗
Decision-making Framework to Support the End-of-Life Management of High-Activity Radioactive Sources
Sealed radioactive sources are used for an extremely wide range of purposes, including as radiation sources in various nuclear facilities, universities, hospitals, biomedical and industrial applications, as well as for geological prospecting and exploration. The proper management of these sealed radioactive sources once they have reached their end-of-life is still a global challenge. Very few field-tested Mobile Hot Cells (MHC) exist in the world to support the end-of-life management of disused high-activity radioactive sources. One of the critical challenges that a source recovery team encounters on each site is to find adequate space, and access to that space to complete the staging and recapture process with a MHC; this process is tedious, uncertain, and time-consuming. Therefore, it is essential to understand the planning and management of the MHC setup and takedown. Currently, there isn't an single capable planning tool that will provide an effective medium to plan, inform, educate, and communicate knowledge about the environment where the MHC will be deployed. We present a novel approach for the planning and management of the deployment of the MHC to several different sites that relies on technology. Furthermore, this planning tool will support collaboration, promote information sharing, and foster better decision making processes, resulting in a more efficient, and reliable setup and source recovery with the MHC.
61 RADIATION PROTECTION AND DOSIMETRY↗
An acid baking approach to enhance heavy rare earth recovery from bituminous coal-based sources
The recovery of rare earth elements (REEs) from secondary resources, particularly coal-based materials, has recently received attention due to supply and demand imbalance. Research reported to date indicates that a high REE recovery can be realized when treating bituminous coal sources using strong acid solutions of approximately100 g/L or higher. This study introduces an approach to enhance the total rare earth recovery (TREE), especially for heavy rare earth elements (HREEs), from these coal sources at significantly lower acid concentrations. Based on the presence of REE minerals like monazite and xenotime, a detailed investigation was undertaken to quantify three pre-leach treatment methods, i.e., 1) roasting, 2) direct acid baking, and 3) acid baking after roasting. Roasting tests at 600°C revealed that the recovery of light REEs (LREEs) was enhanced while the recovery of HREEs remained relatively unaffected. LREE and HREE recovery values of 38.3% and 21.3%, respectively, were achieved using a 50 g/L (0.5 M) sulfuric acid solution at 5% solid concentration and a solution temperature of 75°C for 2 h. Comparatively, direct acid baking at 250°C provided substantial increases in LREE and HREE recovery values to approximately 49.4% and 53.0%, respectively, using an equivalent acid dosage. Recoveries were maximized to 77.0% and 79.6% for LREE and HREE, respectively, by roasting followed by acid baking. Similar results were obtained from the treatment of a second bituminous coal source. Due to strong correlations between REE and Al recovery values, tests were performed on kaolinite and illite, which were prominent clay minerals within the source coals. In conclusion, these experiments revealed that the REE recovery improvements were likely a result of dehydroxylation of clays and subsequent release and decomposition of REE-bearing minerals such as monazite, xenotime and zircon.
42 ENGINEERING↗
Perspectives on Response to an Abnormal Radiological Event [Slides]
On May 2, 2019, a sealed radioactive source containing cesium-137 was breached at the University of Washington Harborview Research and Training (HRT) Building in downtown Seattle while attempting to recover the source for the National Nuclear Security Administration’s (NNSA’s) Off-site Source Recovery Program (OSRP). The breach of the source resulted in the contamination of personnel, large sections of the building, and a release of material to the local environment.
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
Summary of Forensic Examinations in Support of Breach Sealed Source Event at Harborview Medical Facility on 2 May 2019
On May 2, 2019, International Isotopes, Inc. (INIS), a subcontractor to Triad National Security, LLC (contractor for Los Alamos National Laboratory) breached a sealed radioactive source containing ~2800 Ci of the radioactive isotope cesium-137 ( 137 Cs) at the University of Washington Harborview Research and Training (HRT) Building in downtown Seattle while attempting to recover the source for the National Nuclear Security Administration’s (NNSA’s) Off-site Source Recovery Program (OSRP). The breach of the source resulted in the contamination of 13 personnel, all 7 floors of the building, and a release of material to the environment. A summary of root and contributing causes of the event was investigated and published by a joint investigation team (JIT) co-led by NNSA and Triad National Security, LLC. That investigation was supported by forensics examinations provided by Pacific Northwest National Laboratory. This report summarizes the results of those forensic examinations.
61 RADIATION PROTECTION AND DOSIMETRY↗
Being Responsive: Leonard Manzanares
The inked stamps in his passport are testament to the globe-sweeping impact of this source recovery specialist from Los Alamos National Laboratory. His name is Leonard Manzanares, and nuclear and radiological material security is the mission that motivates him wherever he goes, domestically or internationally.
99 GENERAL AND MISCELLANEOUS↗
Reconstruction of Irradiation History of Am-241/Be Startup Sources for Disposal at WIPP - 18644
The National Nuclear Security Administration, Global Material Security (GMS)/ Off-site Source Recovery Program (OSRP) requires an approved final disposition pathway for sealed neutron startup sources with undocumented or questionable irradiation histories. To obtain approval for WIPP disposal, a reliable method is required to determine yields of transmutation, as well as fission and activation products contained within the source at the time of disposal. This paper presents a method to reconstruct the irradiation history of americium beryllium (Am/Be) reactor startup sources using gamma spectroscopy, ORIGEN modeling and the initial composition of the source. Using this method, measured isotopes in the Am/Be startup sources are related to the WIPP disposal requirements. Maximum allowable measurement uncertainties have been quantified and related to uncertainties in the WIPP required isotopes. Characterization calculations and experimental measurements of irradiated Am/Be sources are discussed. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Radsource Mr: Mixed Reality Planning Tool For Radioactive Recovery
The RadSource MR system leverages Meta Quest 3's advanced mixed reality capabilities to create a comprehensive spatial planning platform for end-of-life sealed radioactive source recovery operations. The application utilizes the Quest 3's high-resolution passthrough cameras and spatial mapping algorithms to generate accurate 3D environmental models. Core technical components include: (1) Real-time spatial measurement algorithms calculating distances, angles, slopes, and surface areas with sub-centimeter accuracy; (2) Virtual object placement system allowing users to position digital representations of recovery equipment (trailers, containment vessels, protective barriers) within the real environment; (3) Voice recording and annotation system for hands-free documentation in protective equipment; (4) 3D mesh capture and storage capabilities for post-operation analysis and regulatory documentation. (5) Procedure documentation is available for viewing in Mixed Reality, providing an innovative and convenient way to access the information during pre-visit and inspection activities. (6) Support for screen capture for the view for real world and virtual objects together to use it later for planning. The system integrates computer vision techniques for environmental understanding, spatial mathematics for precise measurements, and human-computer interaction principles optimized for hazardous environment operations. Data persistence allows teams to save and share planning sessions across multiple stakeholders while maintaining operational security requirements.
Khadka, Rajiv [Idaho National Laboratory (INL), Id↗
Detecting Dwarf Galaxies Around NGC 55
Lambda-CDM predicts the existence of faint dwarf galaxies orbiting both large host galaxies, like the Milky Way, and smaller hosts like the Magellanic Clouds. However, the satellite populations around these smaller host galaxies are poorly understood from both a theoretical and observational perspective. In order to improve our understanding of the satellite populations of low-mass galaxies, the DELVE-DEEP Survey is performing a search for satellites around the nearby, low-mass galaxy, NGC 55. As part of this search, we aim to characterize our detection sensitivity by injecting artificial dwarf galaxies into our data set and attempting to recover them. In this poster, I present our methods of injection and recovery, as well as our preliminary results showing our measured detection rates for artificial dwarf galaxies of varying size and luminosity. Additionally, we explore the blending of resolved stellar fluxes that results as a consequence of source recovery and how this affects the recovered magnitudes of injected dwarf galaxies.
79 ASTRONOMY AND ASTROPHYSICS↗
Idaho National Laboratory’s Mobile Hot Cell Transportation: Engineering Solutions for Global Disused Sealed Radioactive Sources.
Title: Idaho National Laboratory’s Mobile Hot Cell Transportation: Engineering Solutions for Global Disused Sealed Radioactive Sources. Abstract: The Mobile Hot Cell (MHC), currently under development by Idaho National Laboratory (INL) for the Off-Site Source Recovery Project (OSRP), is designed to help international partners meet the unique challenges of end-of-life radioactive material management. The MHC will provide a critical resource for countries that require assistance securing and disposing of Disused Sealed Radioactive Sources (DSRS) and orphaned sources in challenging environments, allowing these sources to be secured against misuse and nefarious activities. The MHC is a rapidly deployable system for conditioning and preparing end-of-life radioactive sources for transportation or storage. It is designed to handle sources of up to 1,000 Ci Co-60 equivalent while maintaining full radiological and biological containment. It will be deployable within 48 hours of an alert, making it ideal for emergency situations. The MHC features an operational suite for control, support racks for electronics, pneumatics, and welding systems, and a modular robust steel structure providing radiological shielding and internal robotic support. This design allows configurations for multiple device types to be conditioned and the ability to safely manage routine issues such as leaking or damaged sources. The MHC has been designed with the transportation challenges of rapid deployment to difficult environments in mind. The system weighs approximately 150,000 pounds, with individual systems breaking down into pieces not exceeding 20,000 pounds. Components are to be transportable on standard 20ft ISO containers, with shielding shells on 20ft flat racks. It is estimated that a total of eight containers and flat racks will be required. The use of 20ft containers, as opposed to 40ft containers, minimizes the impact on less developed road infrastructures, enabling the MHC to be positioned in constrained environments such as hospital parking lots. The system’s modularity also allows for deployment using smaller equipment, such as a 10-ton boom truck or forklift, which is crucial given the potential logistical challenges in different countries. This transportation strategy, evaluated in collaboration with Utah State University, ensures the MHC can be deployed via ground, rail, sea, or air, addressing the primary concern of international transport logistics.
99 - GENERAL AND MISCELLANEOUS↗