ALS Bl12022 Endstation (Flangosaurus Endstation) v1.0
CAD drawing of Bl12022 coherent scattering endstation.
Miller, Tom↗
SEARCH · Engineering Papers
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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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Directional Dark Matter Detection With Scintillating Crystals
Dark matter is in every galaxy including our own. Dark matter is composed of non-visible particles which makes it difficult to measure. During this research project I used a Computer Aided Design Software (CAD) called AutoDesk Fusion 360 to create a housing component for a scintillating crystal that would be compatible with the front end of the Astro Dewar holding a CCD. This component allowed us to measure the dark matter UV energy given off by the scintillating crystal.
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
ADDITIVE MANUFACTURING AND REGULATORY TESTING OF CANISTERS FOR SPENT NUCLEAR FUEL MANAGEMENT
The back end of the fuel cycle focuses on the interim storage, transportation, and final disposition of the spent nuclear fuel from nuclear reactors. Commercial light water nuclear power stations across the United States operate with fuel assemblies being irradiated for up to 6 years (planned) in the reactor pressure vessel. After their planned irradiation, the fuel assemblies are moved to a spent fuel pool within the facility complex. After the spent nuclear fuel is removed from the fuel pool, it is typically inserted into a welded metal canister that can be transferred between overpacks for storage, transportation and possibly disposal. Most dry storage systems being used by industry today use dual purpose canisters (DPCs), designed for use in storage and transportation overpacks, but not specifically designed for disposal. Triple purpose-canisters, designed for disposal in addition to storage and transportation, have also been researched. Traditional manufacturing methods for spent fuel canisters involve fusion welding along the length or circumference of the canister which results in high tensile residual stresses in the joint weld zone (WZ) and heat affected zone (HAZ). In this paper, spent fuel canister designs were printed by wire arc additive manufacturing (AM) using the 316L SS welding wire to demonstrate: 1. Feasibility of spent nuclear fuel canister fabrication using this advanced manufacturing method, 2. Dynamic response of the additive manufacture canister design when subjected to the federally mandated Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) physical tests for Type B packages. This paper will focus on the canister printing design and structural tests. The AM 3D printed design, regulatory testing, and post-test evaluation of the canister tested to the 10 CFR 71.71 and 10 CFR 71.73 requirements will be presented. One AM canister design was subjected to the penetration, free drop, and puncture test. Before and after the dynamic structural tests, the AM canister design was scanned with a handheld scanner to capture a 3D CAD geometry to compare to the 3D printed canister design in the deformed shape. The scanned geometry was sectioned in areas with deformation and the cross-section profile was measured to determine accurate and repeated results of the deformed shape of the AM canister design.
Martinez, Oscar↗
Intern Poster Session
This poster has been developed for display during the 2023 Intern Poster Session. The poster is apart of the Nuclear Research and Experiments category. The focus of this poster is on the modifications made to the design of an integral effect test (IET) facility currently being designed for a new Small Modular Reactor (SMR) design. My contributions made to the IET facility are laid out along with an explanation on some of the aspects of designing a new nuclear reactor. This poster covers the ideas and importance of scaling and IET facilities with the context of the standards set by the NRC. There are also graphics of some other examples of IET facilities developed for other reactor designs. My contributions include designing the piping and instrumentation layout of the IET facility using CAD software. This is a key step in the process of designing this IET facility and needs to be designed to avoid excessive head loss.
42 ENGINEERING↗
Optical Investigation of Catalyst Heating Operation in a Light-Duty Compression-Ignition Engine
It is well known that cold start engine operation contributes a majority of tail-pipe emissions during a vehicle drive cycle. Aftertreatment catalysts have poor conversion efficiency during this period due to low conversion efficiency at temperatures less than their light-off temperature. A late post injection strategy, with a delayed injection to increase exhaust enthalpy, can help decrease the time required to heat-up the catalyst. However, late injections into conditions with decreasing temperature and density can result in high emissions and combustion instability. In this study a three-injection strategy with a late-post injection was investigated in an optically-accessible engine. For the first two injections (pilot and main) timing and duration were held constant as the post injection timing was swept and duration varied to hold load constant, at a relevant light-load catalyst heating operating condition. Simultaneous double-pass schlieren and OH chemiluminescence data were acquired in an optically-accessible 0.4 L single-cylinder engine to understand spray characteristics and combustion behavior for #2 diesel fuel. Optical images analysis revealed higher liquid penetration and lower vaporization of the liquid fuel jet as post injection is retarded. It is also observed that retarding post injection timing to +25 CAD resulted in lower observed soot concentration in the piston bowl.
99 GENERAL AND MISCELLANEOUS↗
Inside marginal adaptation of crowns by X-ray micro-computed tomography
The objective of this work was to access dental arcade by using X-ray micro-computed tomography. For this purpose high resolution system was used and three groups were studied: Zirkonzahn CAD-CAM system, IPS e.max Press, and metal ceramic. The three systems assessed in this study showed results of marginal and discrepancy gaps clinically accepted. The great result of 2D and 3D evaluations showed that the used technique is a powerful method to investigate quantitative characteristics of dental arcade. (authors)
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Radiological characterization and Decommissioning of Research and Power Reactors - 15602
The production of the detailed activity and dose rate atlases (ADAs) is one of the indispensable measures in the decommissioning process of nuclear reactors which allows to determine the radiation field for optimal radiation protection as well as to quantify and characterize nuclear waste for disposal. High-detailed simulation models capable of performing neutron and radiation transport calculations at different levels of precision and details are applied for this purpose. Within the framework of the research project 'Decommissioning of Research and Power Reactors', funded by the German Federal Ministry of Education and Research (BMBF), and implemented by the Institute of Nuclear Engineering and Technology Transfer (NET) -RWTH Aachen, sophisticated simulation tools are developed. The enhances capability of these tools for the generation of the activity and dose rate distribution are tested and demonstrated on the shutdown German research reactor FRJ-2. To achieve the project goal different computational steps were required: 1. Development of a calculational CAD-based model for Monte Carlo neutron and gamma transport simulation using converter tool McCad 2. Design of the neutron source which reproduce the neutron distribution leaving the core 3. Enhancement of the simulation performance by using the hybrid deterministic Monte Carlo variance reduction methods 4. Calculation of N-flux distribution in the entire geometry 5. Development of couple codes between MCNP5 and the activation code ORIGEN2.2 This paper describes the main significant project milestones. (authors)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Design of Removable Shield Modules for Nuclear Plant Applications Using Monte Carlo Modeling - 16264
A new modular shielding system has been designed and developed for nuclear plant applications as a replacement for traditional concrete blocks and plugs. The shield comprises interlocking modules that are custom designed using CAD and Monte Carlo modelling methods. The key benefit of these new modules is that they can be quickly removed and re-installed to allow temporary access to high radiation environments e.g. for maintenance and repair of plant equipment at nuclear power plants or waste handling facilities. The traditional method for construction of these removable concrete blocks and plugs was to cast them in place. Within the aging fleet of commercial reactors, some plants are experiencing concrete degradation of these shield blocks and plugs as well as failure of lifting points. Additionally, the existing plugs are difficult to remove and re-install. The new modular system comprises a rigid steel enclosure filled with lead that can be installed in a fraction of the normal time. This approach can accelerate outage times leading to reduced dose uptake to operators and provide significant long term cost savings. Use of Monte Carlo methods enables the shielding modules to be designed efficiently for neutron and gamma ray attenuation with the minimum necessary thickness of lead and steel. Furthermore, the modelling ensures the design is not compromised by streaming pathways, for example at the overlaps between modules or through internal structural components. Shielding modules were supplied to the Brunswick Nuclear Power station (BNP), operated by Duke Energy, located in southeast United States. These modules have been installed to replace concrete shield plugs that are located on the roof above a Feed Water Heaters (FWH) bay. While specific in application, this project demonstrates that the shield module design concept could be expanded to address vertical block walls routinely found in personnel and equipment access hatches. This approach is applicable to a wide variety of new and existing nuclear facilities and will lead to improved safety and reduced lifetime costs all the way through to future decommissioning and dismantling operations. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Predicting Fueled Experiment Swelling and Thermal Expansion Using STAR-CCM+
An experiment being designed at Idaho National Laboratory (INL) has an unusual temperature requirement. The surface temperature must remain above 300 C over the irradiation lifetime. The fuel in this experiment is composed of uranium-nitride (UN) tri-structural-isotropic (TRISO) particles encased in a cylindrical, SiC matrix. Increased swelling of SiC at lower temperatures is the basis for this lower temperature limit. For a typical thermal analysis, the focus is on some upper limit of the center-line temperature. This tends to be a more straight-forward process where the analyst makes a series of worst-case assumptions and demonstrates that the experiment - even under those conditions - cannot exceed the maximum temperature. The model used to ensure the experiment will always have a surface temperature in excess of 300 C has been developed using STAR-CCM+. Notable properties of the simulation include - Full 3D fluid and heat transfer modeling; - Geometry input taken directly from design engineer's CAD files; - Fuel swelling and thermal conductivity as functions of displacements per atom (DPA) and temperature; - Radial thermal expansion of fuel, rodlet, and capsule; - Jump gap and surface roughness implemented using equations from BISON. These things together have yielded a model with sufficient detail to predict minimum surface temperatures with the greatest precision attainable with available data. The only notable approximation is the zirconia insulator, which will actually be a sphere. This particular shape was chosen to expedite meshing, while maintaining a realistic degree of physical contact with adjacent components. Given temperature and irradiation dependent data for thermal conductivity and fuel swelling of a SiC matrix, it was possible to perform an in-depth thermal analysis to find an optimal configuration of radial gas gaps. Of greatest importance was that the fuel surface temperature remain above 300 C. This criteria was met with a healthy margin, even when considering machining tolerances of ±1 mil on the gas gaps.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Port Hope Area Initiative Project Update - 19146
The Port Hope Area Initiative (PHAI) is a federal environmental clean-up program. Its mandate is the remediation and local, long-term, safe management of approximately 1.7 million cubic metres of historic low-level radioactive waste in the adjacent communities of Port Hope and Port Granby in Southern Ontario, Canada. The PHAI is being undertaken by Canadian Nuclear Laboratories (CNL), on behalf of Atomic Energy of Canada Limited, a federal Crown corporation. With funding of $1.28 billion CAD it is currently one of the largest environmental remediation projects in Canada. The safety of workers, the public and the environment while delivering the PHAI on time and within budget is CNL's number one priority. The PHAI is being carried out as two projects - the Port Hope Project and the Port Granby Project. The Port Hope Project is the larger of the two and includes the cleanup of approximately 1.2 million cubic metres of historic waste from various locations within the community. The Port Granby Project will relocate approximately 450,000 cubic metres of historic low-level radioactive waste and marginally contaminated soils, located at an existing waste management facility on the shoreline of Lake Ontario, to a new engineered aboveground mound being built about a kilometre north of the current site. This paper will provide an update on both projects with an emphasis on successes to date and challenges yet be faced. (authors)
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
Application of a Deep Learning Network to 3D Modeling of Nuclear Facilities - 19614
The ultimate goal of this study is to minimize (or eliminate) human intervention in the scanning and 3D CAD modeling process in the generation of 3D as-built model of nuclear facilities. This paper describes the application of the state-of-the-art deep learning technology in 3D point cloud data segmentation which is a part of the 3D modeling process. The baseline deep learning network chosen in this study is PointNet. We compare the deep learning approach with a conventional filtering approach, and show the feasibility and potential of deep learning technology. (authors)
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Mesh Adaptive Search Optimization in SERPENT2 Stereolithography Geometry
SERPENT2 Monte Carlo program has the capability to model reactor cores by stereolithography (STL) geometry. In this geometry, volumes are defined by the union of triangulated surfaces. Using the STL geometry offers unique benefits, including: 1) the model can be printed on 3D printers; 2) the possibility to use directly geometrical models from Computer-Aided Design (CAD); 3) the capability to perform multi-physics simulations coupling neutronics, thermal-hydraulics, and material science computations. In this work the STL geometry has been created by the CUBIT software, which is designed for finite elements mesh generation. The materials in the STL geometry have been assigned by a simple C program using the colors of the volumes in the CUBIT model. The goal of this work is to minimize the SERPENT2 computing time using mesh adaptive search algorithms. The basic idea is to split the geometry of the core into two zones: one zone containing the fuel elements (including the moderator and the coolant) and the other containing the reflector (and the target zone of the core, if it is driven by an external neutron source). By performing this splitting, two separate meshes are used, which results in a considerable computing time saving. (authors)
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Recovering Topology of Nested Volumes Represented by Single Closed Surfaces
As scientific computing abilities continue to advance, so too have the efforts to model and simulate highly complex geometries in radiation environments. Modeling has advanced from primitive constructive solid geometry (CSG) to voxelized models, and now to high fidelity polygon mesh models. While polygon mesh surface models are very accurate, most Monte Carlo codes do not allow for their direct use. Often they are converted to voxel or tetrahedral mesh models and then used with the physics codes. The Direct Accelerated Geometry Monte Carlo (DAGMC) software package has the ability to efficiently run transport calculations directly on tessellated surface models. Typically the surface meshes used for DAGMC calculations come from CAD-based geometry models generated by solid modeling software. In some cases geometries of interest, like human phantoms, are generated by other means and may not contain all of the necessary information for particle transport. For example, mesh geometries in the OBJ file format contain vertex and connectivity data for each surface, but do not have any information about surface topology. These types of file formats necessitate a tool that can build a hierarchy of surfaces and reconstruct the topological information. The generate hierarchy tool was developed for this purpose. The following summary will explain the algorithm behind the tool, describe a test case, and finally demonstrate a real-world application of the tool with an MCNP5 calculation that directly uses a polygon mesh human phantom.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Measurement and Monte Carlo simulation of 3D neutrons distribution in a radiotherapy bunker - 25411
Different methods exist to verify bunkers design for radiation therapy medical facilities; analytical methods based on simplified equations and Monte Carlo methods. One of the main purposes of this work is to present the advantages of using Monte Carlo simulation to verify radiotherapy bunker shielding design. This methodology is more accurate and characterizes not only the fluence and dose three-dimensionally, but also the energy spectrum of particles generated by the Linac. The other main purpose of the work is to analyze the importance of the generated photoneutrons when the Linac emits photon beams of high energy (above 8 MeV), since numerous studies have found that they can expose the patient and clinical staff to non-negligible dose. The main novelty introduced by this work, is the creation of more realistic simulation models to represent the radiotherapy facility by using CAD and meshes technologies. Results obtained using these bunker simulation models have been validated experimentally at the Hospital Universitari i Politecnic La Fe de Valencia facilities using two different neutron detectors; the neutron meter LB 6411 (designed between Berthold and Karlsruhe Research Center) and neutron detector model 42 - 41L (Ludlum, Prescila). Results obtained with Monte Carlo and those measured experimentally fit correctly, validating this analysis methodology. (authors)
61 RADIATION PROTECTION AND DOSIMETRY↗
Optimization of the Shielding of a Canister Loading Machine with the deterministic Code Attila{sup R} - Paper 61
In general shielding components are designed with very conservative assumptions and boundary conditions to cover all possibly occurring situations. This often results in an overestimated shielding design in a lot of different fields of application; the shielding of components will be heavier and more expensive than needed. In most cases an initial shielding calculation in the design process shows an unbalanced shielding effect of the shielded radiation source. Sometimes the dose rate limits are slightly exceeded in several areas. From this arises a need for an optimization of the shielding structure. The goal is to decrease the radiation level in the accessible areas to keep the dose rate limits and to reduce the amount of the used shielding material if possible. Shielding material is moved from areas with higher shielding factors to which with lower ones. The optimization process is shown in an example of a loading machine for vitrified waste in canisters. The design review with an optimization of the shielding geometry was done with the deterministic code Attila{sup R} of the company Transpire, Inc. Attila{sup R} is a powerful tool to calculate and optimize the shielding effect of handling facilities for radioactive materials. It is easy to handle with its CAD integration module and an easy setup of the calculation cases. Areas with a low shielding effect which results in an exceeding of the dose rate limits can be found quickly with the illustration due to an Iso-Dose-Rate-Surface in the 3D Model. In these areas the shielding effect has to be improved. Otherwise there is material, which has no significant influence on the shielding effect and makes the handling facilities heavier and more expensive as needed. The optimization of the shielding design of the canister loading machine in the current case results in lower dose rates outside the facility to keep the dose rate limits. The demand of shielding material could be reduced and resulted in a cost reduction on the facility itself and furthermore in the caring facilities to transport this facility (cranes, etc.). (authors)
42 ENGINEERING↗
LINAC Electrical Cabinets - Structural Analysis
Along LINAC s downstream path is a floor containing various cabinets above the LINAC. Of the dozens of cabinets are 4 specific cabinet types: PFN (pulse-forming network) Module, PFN Power Supply, Water Skid, and Marx. Each of these cabinets may contain some of the various contents that include electronics, wiring, pipe lines, circuits, conduits. In addition, high voltage and flowing fluids are also present within the cabinets. Occasionally, Lab Technicians perform maintenance and inspections of the cabinets and need to access every part, including the top section that is subject to the weight of the technician standing on top. To ensure the cabinet is structurally safe, a CAD model will be developed for each cabinet and a Finite Element Analysis (FEA) will be performed on each cabinet to confirm it is safe to stand on.
Blas, Efren↗
Electrospinner Upgrades for Nanofiber Production
Electrospinning is an inexpensive and flexible method for producing nanofibers. Nanofibers are highly adaptable with potential applications in accelerator target systems, air and water filtration, and biomedicine. This project aims to upgrade and test an existing roll-to-roll electrospinner that is more economical for industrial nanofiber production. Varying the diameter of nanofiber can change its functional properties. The current unit cannot adjust spinneret-collector separation, which determines nanofiber diameter. The electro-spinneret channel also does not have lateral adjustment capabilities for precise alignment. Lastly, the viscosities of our polymer solutions have not been quantified. Solution injection into the channel is presently inconsistent because of imperfect nozzle sizing, resulting in waste and decreased efficiency. Modeling was done with Siemens NX CAD software, and viscosity was measured using a Brookfield DVE-LV viscometer. A dual scissor lift design for channel displacement, powered by a dual-shaft DC motor coupled to precision lead screws, was approved and construction was started. Preliminary channel modifications also were initiated. Going forward, the scissor lift system will be integrated and evaluated with our electrospinner, along with further channel modifications. Viscosity measurements of polyvinyldimethylformamide (PVDF) were recorded with inconsistent results due to inadequate testing conditions. Future viscosity trials must be completed in accordance with testing requirements. The optimization and commercialization of roll-to-roll electrospinner units can make nanofiber production more feasible for many new industries and consumer products.
Black, Niko↗
LINAC Electrical Cabinet - Structural Analysis
Along LINAC s downstream path is a floor containing various cabinets above the LINAC. Of the dozens of cabinets are 4 specific cabinet types: PFN (pulse-forming network) Module, PFN Power Supply, Water Skid, and Marx. Each of these cabinets may contain some of the various contents that include electronics, wiring, circuits, and conduits. In addition, high voltage and low conductivity water (LCW) piping are also present within the cabinets. Occasionally, Lab Technicians perform maintenance and inspections of the cabinets and need to access every part, including the top section that is subject to the weight of the technician standing on top. To ensure the cabinet is structurally safe, a CAD model was developed for each cabinet and a Finite Element Analysis (FEA) was performed on each cabinet to confirm it is safe to stand on.
Blas, Efren↗