Search NASA⌕ Search

SEARCH · Search NASA

Results for “PERSONNEL”

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.

At least 253 records · Page 14
All sourcesNASA NTRSDOE OSTI
DOE OSTI2021

Intelligent Monitoring Systems and Advanced Well Integrity and Mitigation

Long-term seismic monitoring of carbon capture and storage projects is needed to verify that the injected gas is safely stored in the subsurface until permanence can be assured. Conventional surface seismic monitoring techniques are usually expensive, require highly invasive surface operations, and need significant time investments on the part of personnel for both the field effort and processing the acquired data. For these reasons, permanent reservoir monitoring technologies are preferred, as they can offer a cost-effective solution for long-term monitoring. As part of the monitoring program of the Archer Daniels Midland’s large-scale injection of CO 2 in Decatur, Illinois, USA, a continuous seismic monitoring array was installed using a combination of surface orbital vibrator (SOV) sources and fiber-optic cables for distributed acoustic sensing (DAS) acquisition with the objective to build a continuous monitoring array. The aim of the presented project was to build a monitoring array and platform that integrates real-time seismic data with conventional data streams and provides continuous data analysis using dynamic computational models to deliver a comprehensive real-time assessment of subsurface conditions. It is in this context that the Intelligent Monitoring Systems and Advanced Well Integrity and Mitigation project was proposed with the objective to develop an integrated architecture that utilizes a permanent seismic monitoring network, combines the real-time geophysical and process data with reservoir flow and geomechanical models to create a comprehensive monitoring, visualization, and control system that delivers critical information for process surveillance and optimization.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2021

RCT Continuing Training (Q3, 2021) [Slides]

Radiological Control Technicians (RCTs) serve an important part in the mission of Los Alamos National Laboratory by monitoring the diverse radiological conditions at the Lab. The role of RCTs is critical in maintaining personnel safety from radiological hazards and in keeping occupational radiation exposure As low As Reasonably Achievable (ALARA). This training content consists of two parts: viewing an online lecture and completing the associated exercise guide. The online lecture, presented here, will review performing job coverage and all of the necessary steps associated with it.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2021

RCT Continuing Training Presentation Transcript (Q3, 2021)

Radiological Control Technicians (RCTs) serve an important part in the mission of Los Alamos National Laboratory by monitoring the diverse radiological conditions at the Lab. This role is critical in maintaining personnel safety from radiological hazards, and in keeping occupational radiation exposure As Low As Reasonably Achievable (ALARA). This training presentation will review performing job coverage and all of the necessary steps associated with it.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2021

CpRad User's Manual

This is the reference manual for users of the C programming language based proton Radiography simulation package CpRad, pronounced "see p-rad." These simulations are developed and maintained by Los Alamos National Laboratory personnel. Currently there are threaded versions, versions written for MPI, as well as versions that use GPUs. The fundamentals of our proton radiography model are well described in a review. The ray tracing in CpRad also includes the incident angle of the protons based on position in the field of view due to the matching conditions.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2021

Responding To A Downed Unmanned Aircraft System (UAS) Platform

A drone may be forced down as part of a kinetic Counter-UAS action or as a spoof signal with a command to land immediately. A drone could also be incidentally discovered by an employee or by a random patrol. In each case, the platform should be considered a suspicious package until it can be determined to be nonhazardous by qualified personnel.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
DOE OSTI2021

Silicon-Equivalent Neutron Dose Estimations

Radiation transport calculations are often used to estimate dose or exposure to components and personnel surrounding a radiation source. The sources for these calculations are decaying radionuclides within the various nuclear materials. Under long-term radiation exposure, some components may show signs of material damage such as hardening, cracking, discoloration, etc. resulting from the dose received from nearby radioactive sources. Radiation dose quantities are a useful means to correlate material damage or degradation to radiation interactions. The degradation is often dependent on how incident radiation interacts and deposits energy into the material. This dependence implies that radiation dose should be properly defined for the material effect of interest. Generic dose quantities, such as total energy deposited, may not necessarily correlate well for degradation of any given material.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2021

Evaluation of Attila and MCNP computational methods for dose and exposure estimation

Radiation transport calculations are often used to estimate dose or exposure to components and personnel surrounding a radiation source. The sources for these calculations are decaying radionuclides within various nuclear materials. Historically, dose calculations use MCNP (Monte Carlo N-Particle) transport code as the primary particle transport tool without a secondary computational tool to validate the results from the MCNP simulations [1]. The goal of this study is to make an independent check of the Monte Carlo solution from MCNP6 Version 6.2.1 with the discrete ordinates solution from Attila 10.2.0 Beta 3. As an example problem for this study, water-filled, stainless-steel vessels, modeled with an unstructured mesh (UM) with both MCNP and Attila [2], are exposed to 252Cf and 60Co point sources. This report also includes a discussion of the limitations of unstructured mesh in a MCNP calculation.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2021

Oregon Roadway CSZ Liquefaction and Landslide Impact Screening Analysis

The roadway transportation routes and the surrounding environments in Oregon will be subject to ground acceleration and potential associated deformation due to the propagation of waves of energy during a Cascadia Subduction Zone (CSZ) earthquake. Linear features such as highways may be subject to partial or complete disruption of their function resulting from ground deformations at and along the roadway. A potential source of these disruptions associated with a CSZ event are landslides and liquefaction in the soils along and beneath the highways and local roadways. The construction of the Oregon roadway system and urban development have occurred largely along the banks of the rivers—those along the Pacific coast, and along the valleys throughout the Oregon Coast Range and Cascade Mountains. These locations also represent areas where landslides and liquefaction have occurred historically, or may potentially occur in the future, presenting a significant vulnerability for the roadway system and dependent post-CSZ earthquake emergency response and recovery effort. Many of the Oregon areas with landslide- and liquefaction-prone soils have the potential to impact roadway transportation routes after a major earthquake causing delays in establishing routes to transport emergency response personnel and resources to impacted areas and communities. This report presents methods used to project the impacts that CSZ earthquake-induced landslides and liquefaction may have on roadways across Oregon. First, this report presents an approach for estimating the risk of landslides to Oregon roadways, and determining approximate reopening times. Second, this report presents a similar approach for estimating the risk of liquefaction-induced ground displacements to roadway pavements, also resulting in approximate reopening times for roadway segments. The outcomes of these two ground failure analyses serve as inputs to a broader analysis of CSZ earthquake impacts to Oregon’s surface transportation system and its ability to support post-disaster response and recovery activities, as part of the Oregon Transportation Systems Regional Resiliency Assessment Program project (CISA 2021).

58 GEOSCIENCES↗
DOE OSTI2021

Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC

Despite being passive components, concrete structures represent a major capital investment in nuclear power plants. However, some concrete components are critical for the safety and long-term operation of the reactors: the concrete containment building protects the reactors from external aggression. The concrete biological shield (CBS) contains the radiation exiting the reactor to protect equipment and personnel. Depending on the design, the CBS also has a function for supporting the reactor’s systems. This function needs to be ensured in-service and during accident scenarios. After several decades of use, the CBS is exposed to high-energy irradiation over an extended operation time, exceeding the fluence level currently considered detrimental for the concrete’s structural properties. Such conditions occur at different times depending on the reactor’s operation and design. Nevertheless, from the perspective of subsequent license application, it is mandatory to assess the potential effects of prolonged irradiation on concrete. Unlike steel components, concrete structures are built with local constituents (cement, sand, and coarse aggregates) to avoid prohibitive transportation costs. Thus, concrete performance is determined by the tolerance or the susceptibility of its constituents against any aging mechanism. The tolerance against irradiation of the CBSs may vary greatly among the 56 nuclear power plants and 93 nuclear power reactors that form the current US light-water reactor fleet. Irradiation-induced degradation is mainly a result of amorphization-induced expansions of the silicated minerals present in the aggregates. The neutron irradiation–induced expansion varies from one rock-forming mineral to another: well framework–structured silicates (e.g., quartz and feldspars) exhibit higher swelling than chained (e.g., pyroxene) or isolated silicates (e.g., garnet). Silicates make up nearly 90% of the Earth’s crust. Other common minerals present in construction aggregates are carbonates found, for example, in limestone. Irradiated carbonates exhibit only very minor expansions.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2021

Lattice Reinforced Cermet Materials

This project developed ceramic-metal (cermet) composite materials reinforced with embedded metal lattices. The goal of the project was to develop materials that have a higher tensile and compressive strength as well as greater fracture toughness than conventional boron carbide-aluminum cermets. These materials have applications in structural applications as well as advanced vehicle and personnel armors.

36 MATERIALS SCIENCE↗
DOE OSTI2021

Production and Performance of High Sulfur Concentration Waste Glasses (FY21)

In FY21 Savannah River National Laboratory (SRNL) was tasked to investigate the practical aspects of low activity waste (LAW) glass production with high sulfur loading for the Office of River Protection (ORP). Relationships between sulfur solubility, retention, and melter resonance need to be evaluated to refine waste loading limits and the super saturated melting (triple melt, grind, and wash) methodology. The impact of high sulfur concentration on durability and phase stability (crystallization and liquid-liquid immiscibility) during slow cooling also needs to be further evaluated. To accomplish this, SRNL proposed scaled melter testing using simulants with matched physicochemical properties to melter feed, as opposed to laboratory reagents. This type of testing is expected to validate applicability to design parameters and functional criteria expected during unit operations. This work was expected to commence in FY21, with the first melter tests being performed near the end of the FY. However, reduced access to Savannah River Site and personnel availability during the COVID-19 pandemic significantly reduced the amount of time and resources available to perform the task. This report documents the experimental plan and progress towards this task. The following is a summarized list of scheduled testing that will be performed on feed, condensate, cold cap and glass: 1) Melter runs; 2) Product consistency test (PCT); 3) Inductively coupled plasma optical emission spectroscopy (ICP-OES); and 4) Optical (OM) and scanning electron microscopy (SEM).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Tank 50 Salt Solution Sample (2QCY21)

In this Technical Report, the chemical and radionuclide contaminant results from the Second Quarter Calendar Year 2021 (CY21) sample of Tank 50 salt solution are presented in tabulated form. The information from this characterization will be used by Savannah River Remediation (SRR) for the transfer of aqueous waste from Tank 50 to the Saltstone Production Facility (SPF), where the waste will be treated and disposed in the Saltstone Disposal Facility. This Technical Report compares results, where applicable, to SPF Waste Acceptance Criteria (WAC) Limits and Targets that were established at the time the Tank 50 sample was obtained. The chemical and radionuclide contaminant results from the characterization of the Second Quarter CY21 sampling of Tank 50 were requested by SRR personnel via a Task Technical Request (TTR) and details of the testing are presented in the Savannah River National Laboratory (SRNL) Task Technical and Quality Assurance Plan (TTQAP). This Technical Report is part of Deliverable 2 relating to Task 1 from the SRR request. Data pertaining to the regulatory limits for Resource Conservation and Recovery Act (RCRA) metals per Task 2 from the SRR request, will be obtained semi-annually for the 1QCY21 and 3QCY21 Tank 50 samples.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Agile Strategy Living Laboratory Reflection Paper

Getting my team members to all agree that we needed to pursue possible solutions for our documentation review process was an idea that came across very well with the team. This specific topic has be something that as a team we have been having struggles with recently due to the shear amount of documents that have been flowing through the team’s hands to review. We all realized that the process had areas that we could change that would eliminate confusion for new employees, reduce backload, and improve efficiency and quality of the documentation reviews. The key personnel on our team that have the most direct control and impact over this process are the production control specialists, documentation preparation and review is their primary job function. They are denoted in the action pack as “doc spec 1” and this individual has 12 years of expertise in their role. The engineers are denoted as “engineer 1, 2, 3” respectively. Engineer 1 has 10 years of experience in this team, engineer 3 has 38 years of experience on the team, and engineer 2 is myself with 5 years of expertise with this team and 5 with the department of defense.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗
DOE OSTI2021

Material Compatibility of Elastomers Used in the Salt Waste Processing Facility(SWPF)

Near the beginning of calendar year 2021, Salt Waste Processing Facility (SWPF) processed nearly a million gallons of initially diluted, and subsequently undiluted, supernatant. Higher than usual levels of Isopar L were detected in the Decontaminated Salt Solution (DSS). After shutting down the process and inspecting the DSS coalescers, personnel discovered the coalescers media appeared deformed and at least one had extruded out of the sealing surfaces. The gasket material was removed and sent to the Savannah River National Laboratory to possibly determine the cause of gasket degradation. A memorandum was issued documenting the results that could not rule out assembly error of the coalescer. For example, over torquing the gaskets beyond their recommended degree of compression, may have been a potential failure mode. SRNL recommended performing a quick compatibility test between the different process solutions used at SWPF and four different polymeric materials (the fifth one-Kalrez ® -arrived at the end of this test).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Operational and Mission Highlights: A Monthly Summary of Top Achievements September 2021

Laboratory personnel working on a years-long Confinement Vessel Disposition (CVD) Project at the Chemistry and Metallurgy Research (CMR) facility recently shipped its first vessel after closing the emptying and dispositioning portion of the project in 2020. During the 1970s and 1980s, the Laboratory conducted experiments that produced data used in computer modeling. Scientists used these models to evaluate the performance of nuclear weapons.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
DOE OSTI2021

Outgoing Vehicle Process Knowledge Document

The following SNL document contains requested forms related to used equipment, as part of the documentation for the MLU shipment that was performed by the LANL MLU team and Crane Services personnel.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2021

Soil Sampling Results for Closure of a Portion of Solid Waste Management Unit #16

This report presents the results of the sampling effort and documents all associated field activities including borehole clearing, soil sample collection, storage and transportation to the analytical laboratories, borehole backfilling and surface restoration, and storage of investigation-derived waste (IDW) for future profiling and disposal by SNL/CA waste management personnel.

54 ENVIRONMENTAL SCIENCES↗