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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.
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EVALUATION OF HUMAN INTERACTION WITH AUTOMATION: EXPLORING POTENTIAL IMPLICATION TO SECURITY OF RADIOACTIVE SOURCES.
Abstract not provided.
A Risk-Based Methodology for the Prioritization of Radioactive Sources.
Abstract not provided.
Managing Cybersecurity Supply Chain Risks for the Security of Radioactive Sources [Slides]
Abstract not provided.
Applying Lessons Learned From the COVID‐19 Global Pandemic to Increase Radioactive Source Security System Resilience.
Abstract not provided.
Prioritizing Radiological Threats: Frameworks for Assessing Risks to Radioactive Materials.
Abstract not provided.
Results for Gamma-Ray Spectroscopy Characterization of Residual Radioactivity on Personal Protective Clothing
In early 2019, Health Physics Services (HPS) personnel put together a test plan to use the shielded gamma-ray spectroscopy instruments in the Health Physics Services Technical Laboratory (HPSTL) to perform a series of measurements on laundered personal protective clothing used in radiological areas at the Savannah River Site (SRS). That test plan describes the methodology used to determine the quantities of laundry to be obtained from operational facilities, the methods for quality control checking the instruments throughout the measurement period, and the physical arrangement of samples in the counting shields. The test plan is documented in SRNS-J6700-2019-00037 (Reference 1).
Application of Process Chemical Modeling to Optimize Radioactive Waste Disposal at the Savannah River Site - 24242
The Technical Optimization Model (TOM) is used by Savannah River Mission Completion (SRMC) to carry out facility-wide material balance and validate chemistrydependent processes for the purpose of their System Plan.The TOM simulates material movement and chemical reactions at the Tank Farm (TF), Salt Waste Processing Facility (SWPF) and Defense Waste Processing Facility (DWPF).
RCT Continuing Training: Radioactive Sealed Sources [Slides]
Abstract not provided.
Ground Truth Measurements and Forensic Analysis After an Explosive Dispersal of Radioactive Materials
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Analysis of Radioactive 65 Zn Contamination using 3D Position Sensitive CdZnTe Detectors
SRNL NMG Goal: In collaboration with ORNL, the aim is to identify and explore innovative technology opportunities that accelerate disposition, reduce life cycle costs, minimize worker radiation exposure, and improve worker safety and minimize program risks. • This process will include 3 glovebox systems that require personnel to dilute and package the plutonium for safe storage at WIPP. • For holdup monitoring and verification, gamma ray spectroscopy and imaging are the methods employed to achieve real time analysis of the plutonium waste. 2
Managing Risks for Radioactive Materials in Transport: Understanding Likelihoods and Consequences
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Gaps in the Radioactive Material Transportation Security Regulatory Process
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Technical Exchange on Security by Design for Devices and Facilities that use Radioactive Material
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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.
Determination of 2,4-Dinitrophenol (2,4-DNP) in Simulated Radioactive Waste by High Performance Liquid Chromatography
The River Protection Project (RPP) at Hanford, Washington is evaluating an alternative treatment method for low activity tank waste (LAW) disposition. Specifically, grout solidification/immobilization for LAW needs to demonstrate adequate treatment for Land Disposal Restricted (LDR) Organic chemicals. LDR organic chemical pretreatment, such as evaporations testing and oxidation decomposition, are under assessment to reduce the LDR organic chemicals concentration in the LDR waste. 2,4-dinitrophenol was spiked into LAW simulated waste and monitored in these studies using High Performance Liquid Chromatography (HPLC). The development and implementation of this HPLC method is discussed in this presentation.