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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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This curriculum is intended to teach about administrative authorizations, explain the course subjects in detail, and provide references and guides to help after viewing the training.
This curriculum is intended to: Teach you about the Engineering Evaluation Process; Explain the course subject in detail; and Provide references and guides that will help beyond this training.
This curriculum is intended to: Teach you about Exception Authorization; Explain the course subject in detail; and Provide references and guides to help you after viewing the training.
This curriculum is intended to: Teach you about the Engineering Evaluation Authorization; Explain the course subject in detail; and Provide references and guides that will help beyond this training.
This curriculum is intended to: Teach you about the Product Definition Authorization; Explain the course subject in detail; and Provide references and guides that will help beyond this training.
This curriculum is intended to: Teach you about Change Product Definition Authorization; Explain the course subject in detail; and Provide references and guides to help you after viewing the training.
This curriculum is intended to: Teach you about the Engineering Authorization (EA) System; Explain the course subject in detail; Provide references and guides that will help beyond this training.
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This document contains an evaluation of the applicability of the current Quality Assurance Standards from the American Society of Mechanical Engineers Standard NQA-1 (NQA-1) criteria and identifies and describes the quality assurance process(es) by which attributes of historical, analytical, and other data associated with sodium-cooled fast reactor [SFR] metallic fuel will be evaluated. This process is being instituted to facilitate validation of data to the extent that such data may be used to support future licensing efforts associated with advanced reactor designs. The initial data to be evaluated under this program were generated during the US Integral Fast Reactor program between 1984-1994, where the data includes, but is not limited to, research and development data and associated documents, test plans and associated protocols, operations and test data, technical reports, and information associated with past United States Nuclear Regulatory Commission reviews of SFR designs. It is recognized that managing the data generated by large research and development projects presents a significant challenge for retaining data integrity and availability. American Society of Mechanical Engineers Standard NQA-1 (NQA-1) 2008/2009a provides appropriate requirements for this plan.
This project builds upon knowledge gained from previous projects on Additive Manufacturing (AM) operation, process control and monitoring, repeatability, and process improvement. This project will exclusively focus on metal powder bed additive manufacturing (PBAM). Objective 1: Advance metal powder bed AM R&D capabilities. Perform enhanced R&D on increased build volumes and throughput, safety and handling controls, process monitoring, and diagnostics with a focus on production end-states. Objective 2: Build upon knowledge gained from previous PDRD projects to develop deeper understanding of process controls, essential for transitioning metal AM processes for future applications. Objective 3: Maintain business development and research advantages through collaborations with external industry and university partners.
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The RCT training program prepares Radiological Control Technicians to support the advancement of the laboratory’s mission objectives while ensuring the health and safety of the workforce and public from radiological hazards, utilizing a multi-disciplinary, hands-on approach. Currently located at the MESA complex within the University of New Mexico – Los Alamos Campus, the RP Training department has established an immersive training environment that simulates realistic work conditions in which RCTs may develop the fundamental knowledge and skills required to control radiological work across the Laboratory
Abstract not provided.
For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) tests the applicability of the digestion methods used by the DWPF Laboratory for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) Receipt samples and SRAT Product process control samples. DWPF SRAT samples are typically dissolved using a method referred to as the DWPF Cold Chemical or Cold Chem Method (CC), (see DWPF Procedure SW4-15.201- 2.1).