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At least 1,243 records · Page 69

Small Unmanned Aerial Systems (sUAS) on the NNSS White Paper

The Nevada National Security Site (NNSS) prides itself on being the premier outdoor, indoor, and underground national laboratory. It is the preferred location for experiments supporting the National Nuclear Security Administration’s nuclear weapons Stockpile Stewardship Programs, national defense programs, and national security research, development, and training programs, as well as vital programs of other federal agencies. Work at the NNSS supports the Stockpile Stewardship Program, Global and Homeland Security programs, and Environmental Management. The NNSS looks to incorporate safer work practices and continuous improvements. Unmanned Aerial Surveys (UAS) have already been implemented in areas off the NNSS for multiple uses. Using these best practices with systems catered to the NNSS would allow integration of new technology and would allow work at the NNSS to maintain the high level of quality already exhibited. The Management and Operating Contractor (M&O) has shown experience in multiple UAS platforms. Through the coordination and experience developed through these projects, the M&O can further improve the quality and cost effectiveness of services currently rendered and offer new services not currently available today. Several NNSS departments that could implement UAS technology are Emergency Response, Facility Management, Environmental Management, and Training. These departments would be able to improve their capabilities and expand personnel effectiveness with the inclusion of UASs and the information they provide.

61 RADIATION PROTECTION AND DOSIMETRY↗

Study of Multi-Scale Cloud Processes Over the Tropical Western Pacific Using Cloud-Resolving Models Constrained by Satellite Data

Clouds in the tropical western Pacific are an integral part of the large scale environment. An improved understanding of the multi-scale structure of clouds and their interactions with the environment is critical to the ARM (Atmospheric Radiation Measurement) program for developing and evaluating cloud parameterizations, understanding the consequences of model biases, and providing a context for interpreting the observational data collected over the ARM Tropical Western Pacific (TWP) sites. Three-dimensional cloud resolving models (CRMs) are powerful tools for developing and evaluating cloud parameterizations. However, a significant challenge in using CRMs in the TWP is that the region lacks conventional data, so large uncertainty exists in defining the large-scale environment for clouds. This project links several aspects of the ARM program, from measurements to providing improved analyses, and from cloud-resolving modeling to climate-scale modeling and parameterization development, with the overall objective to improve the representations of clouds in climate models and to simulate and quantify resolved cloud effects on the large-scale environment. Our objectives will be achieved through a series of tasks focusing on the use of the Weather Research and Forecasting (WRF) model and ARM data. Our approach includes: - Perform assimilation of COSMIC GPS radio occultation and other satellites products using the WRF Ensemble Kalman Filter assimilation system to represent the tropical large-scale environment at 36 km grid resolution. This high-resolution analysis can be used by the community to derive forcing products for single-column models or cloud-resolving models. - Perform cloud-resolving simulations using WRF and its nesting capabilities, driven by the improved regional analysis and evaluate the simulations against ARM datasets such as from TWP-ICE to optimize the microphysics parameters for this region. A cirrus study (Mace and co-authors) already exists for TWP-ICE using satellite and ground-based observations. - Perform numerical experiments using WRF to investigate how convection over tropical islands in the Maritime Continent interacts with large-scale circulation and affects convection in nearby regions. - Evaluate and apply WRF as a testbed for GCM cloud parameterizations, utilizing the ability of WRF to run on multiple scales (from cloud resolving to global) to isolate resolution and physics issues from dynamical and model framework issues. Key products will be disseminated to the ARM and larger community through distribution of data archives, including model outputs from the data assimilation products and cloud resolving simulations, and publications.

54 ENVIRONMENTAL SCIENCES↗

SU-E-P-07: Evaluation of Productivity Systems for Radiation Therapy

Purpose: Health systems throughout the United States are under increased financial pressure to reduce operating cost. As a result, productivity models developed by third-party consultants are being used to optimize staff to treatment volumes. The purpose of this study was to critically evaluate productivity systems for radiation oncology. Methods: Staffing efficiency was evaluated using multiple productivity models. The first model evaluated staffing levels using equal weighting of procedure codes and hours worked. A second productivity model was developed using hours worked by job class and relative value units for each procedure code. A third model was developed using the measured procedure times extracted from the electronic medical record, which tracks the wait and treatment times for each patient for each treatment fraction. A MatLab program was developed to query and analyze the daily treatment data. A model was then created to determine any theoretical gains in treatment productivity. Results: Productivity was evaluated for six radiation therapy departments operating nine linear accelerators delivering over 40,000 treatment fractions per year. Third party productivity models that do not take into consideration the unique nature of radiation therapy can be counterproductive. For example, other outpatient departments can compress their daily schedule to decrease the worked hours. This approach was tested using the treatment schedule evaluation tool developed as part of this study. It was determined that the maximum possible savings for treatment schedule compression was $32,000 per year per linac. All annual cost savings would be lost if only two patients per year choose to be treated elsewhere because of limited or restricted appointment times. Conclusion: The use of productivity models in radiation therapy can easily result in a loss of treatment revenue that is greater than any potential cost savings in reduced hours worked by staff.

60 APPLIED LIFE SCIENCES↗

NICA at JINR: New prospects for exploration of quark-gluon matter

A new scientific program is proposed at the Joint Institute for Nuclear Research (JINR) in Dubna aimed at studies of hot and dense baryonic matter in the wide energy range from 2 GeV/u kinetic energy in fixed target experiments to {radical}s{sub NN} = 4 - 11 GeV/u in the collider mode. To realize this program the development of the JINR accelerator facility in high-energy physics (HEP) has been started. This facility is based on the existing superconducting synchrotron-the Nuclotron. The program foresees both experiments at the beams extracted from the Nuclotron, and the construction of a heavy-ion collider-the Nuclotron-based Ion Collider fAcility (NICA) which is designed to reach the required parameters with an average luminosity of L = 10{sup 27} cm{sup -2} s{sup -1}.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Oscilloscope Data Push Program

This paper details the development of a Python program designed to automate the data acquisition and conversion for an oscilloscope for the purposes of a one-off/temporary data acquisition system for users that readily need data, and do not have the option of obtaining a Data Acquisition (DAQ) solution. Creating DAQ systems for analyzing a system requires expensive electronics and a dedicated team of engineers for support. Traditionally, manual data collection and processing are time consuming and prone to error. By automating these processes, the cost, efficiency and accuracy of data handling are improved upon. This project involves the creation of a program that interacts with the oscilloscope. During this interaction, there are various functions being performed such as the acquisition of waveform data via floating points, generating plots with the acquired wave points, and storing of floating points in a CSV file format for future reference and plotting purposes. While the initial aim of the project included continuous logging to a cloud database, this was deferred due to time constraints. The results portrayed an almost-instant rate of data collection with a buffer time, showcasing the potential for further integration and real-time data processing.

Osei-Tutu, Jason↗

Cross Section Evaluation for Exclusive Channels of K+Λ and K+Σ0 Electroproduction off Protons Using CLAS Detector Data

In this work, a method for evaluating the cross sections of electroproduction of K+Λ0 and K+Σ0 off protons in the region of invariant masses of final hadrons MK + MY <W < 2.65 GeV (MK and MY being the masses of the kaon and hyperon, respectively) and squares of four-momentum transfers of virtual photons, i.e., photon virtualities 0 < Q2 < 5 GeV2, is developed based on experimental data of these exclusive channels’ cross sections measured by the CLAS detector in Hall B at Jefferson Lab. A set of algorithms has been implemented to evaluate the differential cross sections of these channels, along with their statistical and systematic uncertainties. A program was developed for the evaluation of differential cross sections and structure functions using C++ and Python libraries. An interactive website was created for working with the program, enabling the analysis of one-dimensional and two-dimensional dependences of structure functions and differential cross sections. The evaluation of differential cross sections for the K+Λ and K+Σ0 electroproduction channels is necessary for extracting the structure function σLT from the data on the polarization asymmetry of electroproduction reactions of these final states with longitudinally polarized electrons. The obtained results are also important for the development of realistic Monte Carlo event generators in planning future experiments and for evaluating the efficiency of detecting final particles when extracting reaction cross sections from experimental data.

Golda, A. V.↗

SU-E-J-162: Quality Assurance Procedures for MR Guided Focused Ultrasound Treatment of Bone Metastasis

Purpose: The purpose of this work is to develop and verify our quality assurance (QA) procedures to ensure the safety and efficacy of MR-guided focused ultrasound (MRgFUS) treatment of bone metastases. Methods: A practical QA program was developed. Monthly and daily QA (DQA) procedures were performed. The major QA items included the checks of the machine hardware, software and patient safety features. Briefly, these checks/tests include: 1) the cooling system reservoir and treatment table; 2) power to the treatment table; 3) the MR coil; 4) the transducer position with MRI; 5) image display on the treatment work station; 6) the effective focal spot in 3 directions using MR thermometry; and 7) all the safety devices including a sonication lamp, and the emergency stop-sonication switches. In order to avoid patient skin burn, it is important to remove gas bubbles in the interfaces between the treatment table and the gel pad, and the gel pad and patients skin during the patient setup. Our QA procedures have been verified and evaluated through patient treatments. Seven patients with scapula, humeral head, sacrum, ilium, pubic ramus and acetabular bone metastases were treated using MRgFUS. Results: Our study showed that all seven patients tolerated the MRgFUS treatment well. No skin toxicity or other complications were observed. The pain score (0–10) using the visual analog scale (VAS) was significantly reduced from 8.0 ± 1.1 before treatment to 4.7 ± 3.0, 3.0 ± 1.5, 3.2 ± 2.8 and 3.4 ± 1.5 at one day, one month, two months and three months after the MRgFUS treatment, respectively. Conclusion: We demonstrated that with the appropriate QA procedures, MRgFUS is a safe, effective and noninvasive treatment modality for palliation of bone metastases.

60 APPLIED LIFE SCIENCES↗

THE IMPACT OF OZONE ON THE LOWER FLAMMABLE LIMIT OF HYDROGEN IN VESSELS CONTAINING SAVANNAH RIVER SITE HIGH LEVEL WASTE

The Savannah River Site, in conjunction with AREVA Federal services, has designed a process to treat dissolved radioactive waste solids with ozone. It is known that in this radioactive waste process, radionuclides radiolytically break down water into gaseous hydrogen and oxygen, which presents a well defined flammability hazard. Flammability limits have been established for both ozone and hydrogen separately; however, there is little information on mixtures of hydrogen and ozone. Therefore, testing was designed to provide critical flammability information necessary to support safety related considerations for the development of ozone treatment and potential scale-up to the commercial level. Since information was lacking on flammability issues at low levels of hydrogen and ozone, a testing program was developed to focus on filling this portion of the information gap. A 2-L vessel was used to conduct flammability tests at atmospheric pressure and temperature using a fuse wire ignition source at 1 percent ozone intervals spanning from no ozone to the Lower Flammable Limit (LFL) of ozone in the vessel, determined as 8.4%(v/v) ozone. An ozone generator and ozone detector were used to generate and measure the ozone concentration within the vessel in situ, since ozone decomposes rapidly on standing. The lower flammability limit of hydrogen in an ozone-oxygen mixture was found to decrease from the LFL of hydrogen in air, determined as 4.2 % (v/v) in this vessel. From the results of this testing, Savannah River was able to develop safety procedures and operating parameters to effectively minimize the formation of a flammable atmosphere.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

MO-G-BRE-04: Automatic Verification of Daily Treatment Deliveries and Generation of Daily Treatment Reports for a MR Image-Guided Treatment Machine

Purpose: Two aims of this work were to develop a method to automatically verify treatment delivery accuracy immediately after patient treatment and to develop a comprehensive daily treatment report to provide all required information for daily MR-IGRT review. Methods: After systematically analyzing the requirements for treatment delivery verification and understanding the available information from a novel MR-IGRT treatment machine, we designed a method to use 1) treatment plan files, 2) delivery log files, and 3) dosimetric calibration information to verify the accuracy and completeness of daily treatment deliveries. The method verifies the correctness of delivered treatment plans and beams, beam segments, and for each segment, the beam-on time and MLC leaf positions. Composite primary fluence maps are calculated from the MLC leaf positions and the beam-on time. Error statistics are calculated on the fluence difference maps between the plan and the delivery. We also designed the daily treatment delivery report by including all required information for MR-IGRT and physics weekly review - the plan and treatment fraction information, dose verification information, daily patient setup screen captures, and the treatment delivery verification results. Results: The parameters in the log files (e.g. MLC positions) were independently verified and deemed accurate and trustable. A computer program was developed to implement the automatic delivery verification and daily report generation. The program was tested and clinically commissioned with sufficient IMRT and 3D treatment delivery data. The final version has been integrated into a commercial MR-IGRT treatment delivery system. Conclusion: A method was developed to automatically verify MR-IGRT treatment deliveries and generate daily treatment reports. Already in clinical use since December 2013, the system is able to facilitate delivery error detection, and expedite physician daily IGRT review and physicist weekly chart review.

60 APPLIED LIFE SCIENCES↗

The AGR-3/4 fission product transport irradiation experiment

AGR-3/4 was the combined third and fourth planned irradiations for the U.S. Department of Energy Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The primary purpose of the AGR program is to support the development and qualification of tristructural isotropic (TRISO) coated particle fuel for use in High Temperature Gas-cooled Reactors. AGR-3/4 was designed as a fission product transport irradiation experiment whose specific objectives were to: (1) irradiate fuel containing UCO (uranium oxycarbide) designed-to-fail (DTF) fuel particles that provide a fixed source of fission products for subsequent transport through compact matrix and structural graphite materials, (2) assess the effects of sweep gas impurities on fuel performance and fission product transport, (3) provide irradiated fuel and material samples for post-irradiation examination and post-irradiation heating, and (4) support the refinement of fuel performance and fission product transport models. The AGR-3/4 test train was irradiated in the northeast flux trap of the Advanced Test Reactor at Idaho National Laboratory for 369.1 effective full power days from December 2011 to April 2014. The experiment was successful in achieving its specification goals in terms of burnup and fast fluence levels reached at the end of irradiation and fuel temperature levels maintained throughout irradiation: peak compact burnup reached 15.27% fissions per initial heavy-metal atom and peak compact fast fluence reached 5.32 × 10 25 n/m 2 (E > 0.18 MeV), while the time-average volume-average temperatures of the compacts ranged from 854 to 1345°C. Fission product release to birth ratios reached values in the 10 -4 - 10 -3 range early during irradiation as the DTF particles started to fail. In conclusion, subsequent post-irradiation examination will provide information on fission product distributions in matrix and core graphite materials, enabling refinement of fission product transport models.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

ASC Co-design Proxy App Strategy

The NNSA labs representing the ASC program are coordinating on the development and release of a portfolio of proxy applications to be used in co-design. While each lab will develop their own set of proxy apps that represent the applications and algorithms of interest to them, we propose a common set of criteria to describe and measure proxy apps, and a strategy aimed at minimizing duplication and maximizing impact across the entire ASC proxy app portfolio. Proxy application (or proxy apps for short) is a catchall term for the simplification of characteristics of real applications that are of interest to DOE. These proxy apps are used in the co-design process as concrete examples for component and system designers to understand our software requirements. The proxy apps are generally openly available to the co-design community and, unlike benchmarks, are intended to facilitate the two-way communication required by co-design to optimally evaluate trade-offs in the system hardware, and inform the developer community of programming best practices for emerging architectures.

97 MATHEMATICS AND COMPUTING↗

Light Water Reactor Sustainability Program

The Computer-Based Procedure (CBP) research effort is a part of the Light Water Reactor Sustainability (LWRS) Program The LWRS program is a research and development (R&D) program sponsored by Department of Energy (DOE) and performed in close collaboration with industry R&D programs that provides the technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants. One of the primary missions of the LWRS program is to help the U.S. nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

A New Generation High Density Thermal Battery Based on Advanced Metal Hydride

In a world that is facing an energy crisis and environmental pollution, the development of an electric vehicle (EV) as zero-emission, energy-efficiency mode of transportation has taken on an accelerated pace. Most of major automotive manufacturers have launched aggressive programs to develop new-generation EVs, and some economical EVs have been commercialized. Moreover, market forecasting has suggested that Hybrid Electric Vehicles (HEVs), Plug-in Hybrid Electric Vehicles (PHEVs), and Electric Vehicles (EV), will be a growing component of the US vehicle fleets in the near future. By supplying power to EV, a rechargeable electric battery is one of the most crucial components in EV. However, the capacity and cost of an electric battery represent the highest barriers to wide scale adoption of electric vehicles as the large and expensive batteries needed to provide significant driving range can result in unattractive vehicle design and price points. In addition to the electric energy that has been used in powertrain, a key drain on the electrical battery system of an EV is needed to serve cabin heating and cooling loads. Cabin climate conditioning can significantly reduce the electric range of plug-in and full electric vehicles, by as much as 40% in extreme cases, or inversely and can increase the battery size and cost by a comparable amount for the same range. Therefore, significant reduction in the size/cost of EV batteries or a significant increase in driving range can be enabled by eliminating the need for cabin climate load to draw on the electrical battery system. The work of this project focused on a concept that employs metal hydride materials and chloride-ammonia as energy storage materials to build a new generation thermal battery with sufficient energy density to meet the above requirements. The high-energy density of metal hydride material makes the thermal battery meet the requirements of HVAC system for EB automobiles. The present research focused on a specific on-board application to develop a novel HVAC system for EV. However, the methodology of the thermal battery could be extended to a much broader range of applications, including other transportation vehicles such as long haul trucks, stationary HVAC, solar thermal energy storage systems, and waste heat recovery and storage systems. Multiple prototypes were designed, fabricated, and tested. The results successfully demonstrate the principles of the thermal battery using advanced metal hydrides. The performance of the concept-demonstration-unit showed both high heating/cooling power and high energy densities. Although the feasibility of the “Thermal Battery” has been demonstrated by this project, the commercial applications of this technology remain challenging. Either the volumetric or the gravimetric energy density of the materials used often cannot be both met. The solution to this problem is to work with vehicle HAVC designers to identify design innovations that can take advantages of the thermal battery without compromising the performance of the vehicles.

25 ENERGY STORAGE↗

AGR 3/4 Irradiation Test Final As Run Report

Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5×1025 n/m2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the temperature in the twelve capsules relatively flat in a range of temperatures suitable for the measurement of fission product diffusion in compact matrix and structural graphite materials.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

1.5 MW RF Load for ITER

Calabazas Creek Research, Inc. developed a 1.5 MW RF load for the ITER fusion research facility currently under construction in France. This program leveraged technology developed in two previous SBIR programs that successfully developed high power RF loads for fusion research applications. This program specifically focused on modifications required by revised technical performance, materials, and assembly specification for ITER. This program implemented an innovative approach to actively distribute the RF power inside the load to avoid excessive heating or arcing associated with constructive interference. The new design implemented materials and assembly changes required to meet specifications. Critical components were built and successfully tested during the program.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Bio Diesel Cellulosic Ethanol Research Project

The objective of the project is to create the Hendry County Sustainable Biofuels Center and initiate its research, development, and education programs. The mission is to develop engineering and economic assessment methods to evaluate the natural resources impacts of biomass farming and fuel conversion systems; provide sustainability assessments of specific biofuels productions proposals; develop biomass farming and fuel conversion systems that are compatible with south Florida ecosystem restoration priorities; create ecosystem services opportunities and structures to diversify farm income; monitor the range of research and development activities necessary to the creation of sutstainable biofuels production systems in south Florida, identify gaps in the regional research, and assist in the development and coordination of additional projects to fill out the required knowledge base; prepare the workforce of southwest Florida for employment in biofuels related professions; and assist businesses & governmental design and realize sustainable biofuels projects.

09 BIOMASS FUELS↗

AGR 3/4 Irradiation Test Final As Run Report, Revision 1

Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5 × 10 25 n/m 2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the temperature in the twelve capsules relatively flat in a range of temperatures suitable for the measurement of fission product diffusion in compact matrix and structural graphite materials.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗