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At least 1,459 records · Page 81

NEUTRONIC ANALYSES TO SUPPORT WASTE MANAGEMENT FOR SNS

According to the Spallation Neutron Source (SNS) operations plan the facility components are replaced, when they reach their end-of-life. These components must be safely removed, placed in a container for storage, and transported from the site. In order to classify components and suggest appropriate shipping container an accurate estimate of the radionuclide inventory is performed. After choice for the container is made, it is being modelled with the facility component, placed inside, in order to perform transport calculations to ensure that the container is compliant with the waste management regulations

Popova, Irina I↗

Advances in Neutron Radiography: Application to Additive Manufacturing Inconel 718

Reactor-based neutron radiography is a non-destructive, non-invasive characterization technique that has been extensively used for engineering materials such as inspection of components, evaluation of porosity, and in-operando observations of engineering parts. Neutron radiography has flourished at reactor facilities for more than four decades and is relatively new to accelerator-based neutron sources. Recent advances in neutron source and detector technologies, such as the Spallation Neutron Source (SNS) at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN, and the microchannel plate (MCP) detector, respectively, enable new contrast mechanisms using the neutron scattering Bragg features for crystalline information such as average lattice strain, crystalline plane orientation, and identification of phases in a neutron radiograph. Additive manufacturing (AM) processes or 3D printing have recently become very popular and have a significant potential to revolutionize the manufacturing of materials by enabling new designs with complex geometries that are not feasible using conventional manufacturing processes. However, the technique lacks standards for process optimization and control compared to conventional processes. Residual stresses are a common occurrence in materials that are machined, rolled, heat treated, welded, etc., and have a significant impact on a component s mechanical behavior and durability. They may also arise during the 3D printing process, and defects such as internal cracks can propagate over time as the component relaxes after being removed from its build plate (the base plate utilized to print materials on). Moreover, since access to the AM material is possible only after the component has been fully manufactured, it is difficult to characterize the material for defects a priori to minimize expensive re-runs. Currently, validation of the AM process and materials is mainly through expensive trial-and-error experiments at the component level, whereas in conventional processes the level of confidence in predictive computational modeling is high enough to allow process and materials optimization through computational approaches. Thus, there is a clear need for non-destructive characterization techniques and for the establishment of processing- microstructure databases that can be used for developing and validating predictive modeling tools for AM.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Configurable Crossbar Switch for Deterministic, Low-latency Inter-blade Communications in a MicroTCA Platform

As MicroTCA expands into applications beyond the telecommunications industry from which it originated, it faces new challenges in the area of inter-blade communications. The ability to achieve deterministic, low-latency communications between blades is critical to realizing a scalable architecture. In the past, legacy bus architectures accomplished inter-blade communications using dedicated parallel buses across the backplane. Because of limited fabric resources on its backplane, MicroTCA uses the carrier hub (MCH) for this purpose. Unfortunately, MCH products from commercial vendors are limited to standard bus protocols such as PCI Express, Serial Rapid IO and 10/40GbE. While these protocols have exceptional throughput capability, they are neither deterministic nor necessarily low-latency. To overcome this limitation, an MCH has been developed based on the Xilinx Virtex-7 690T FPGA. This MCH provides the system architect/developer complete flexibility in both the interface protocol and routing of information between blades. In this paper, we present the application of this configurable MCH concept to the Machine Protection System under development for the Spallation Neutron Sources's proton accelerator. Specifically, we demonstrate the use of the configurable MCH as a 12x4-lane crossbar switch using the Aurora protocol to achieve a deterministic, low-latency data link. In this configuration, the crossbar has an aggregate bandwidth of 48 GB/s.

97 MATHEMATICS AND COMPUTING↗

6D Phase Space Measurement of Low Energy, High Intensity Hadron Beam

The goal of this project is to demonstrate a method for measuring the full six dimensional phase space of a low energy, high intensity hadron beam. This is done by combining four dimensional emittance measurement techniques along with dispersion measurement and a beam shape monitor to provide the energy and arrival time components. The measurements are performed on the new Beam Test Facility (BTF) at the Spallation Neutron Source (SNS), a 2.5 MeV functional duplicate of the SNS accelerator front end.

Cathey, Brandon L.↗

Analysis and Burnup Modeling of the GEM*STAR Accelerator-Driven System

The purpose of this paper is to evaluate the neutronics and fuel burnup of the GEM*STAR accelerator-driven reactor design. The GEM*STAR design uses a molten salt fuel, with graphite moderation in a subcritical configuration with supplemental neutrons provided by an acceleratordriven proton spallation source. This allows for very safe operation since no criticality accidents are possible. A continuous extraction of spent fuel and addition of fresh fuel allows for the reactor to run at an equilibrium state of power and isotopic concentrations. Further, the liquid fuel and subcritical nature allow for higher burnup and more flexible fueling options. In previous analysis of the reactor, several simplifying assumptions were made about the neutronics modeling. In this study, these assumptions are eliminated, and a more detailed study is performed using MCNP6, Monteburns, and CINDER90 for neutronics and burnup calculation. Although there are some differences between the old and new analyses, equilibrium isotopic concentrations are within 10%, while electric multiplication factors are within 20%. Burnup analysis shows that the approach to equilibrium takes approximately two years for natural uranium fuel. By decreasing the fuel feed rate, the burnup can be increased at the cost of slightly lower electric multiplication. The performance of several feed materials are examined including natural uranium, LWR spent fuel and plutonium.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Electron Beam Profiler for the Fermilab Main Injector

The long range plan for Fermilab calls for large proton beam intensities in excess of 2 MW for use in the neutrino program. Measuring the transverse profiles of these high intensity beams is challenging and generally relies on non-invasive techniques. One such technique involves measuring the deflection of a beam of electrons with a trajectory perpendicular to the proton beam. A device such as this is already in use at the Spallation Neutron Source at ORNL and a similar device will be installed shortly in the Fermilab Main Injector. The Main Injector device is discussed in detail and some test results and simulations are shown

Thurman-Keup, R.↗

Commissioning and First Results of the Electron Beam Profiler in the Main Injector at Fermilab

The planned neutrino program at Fermilab requires large proton beam intensities in excess of 2 MW. Measuring the transverse profiles of these high intensity beams is challenging and often depends on non-invasive techniques. One such technique involves measuring the deflection of a probe beam of electrons with a trajectory perpendicular to the proton beam. A device such as this is already in use at the Spallation Neutron Source at ORNL and a similar device has been installed in the Main Injector at Fermilab. Commissioning of the device is in progress with the goal of having it operational by the end of the year. The status of the commissioning and initial results will be presented

Thurman-Keup, R.↗

Laser System Design and Operation for SNS H- Beam Laser Stripping

Recently, a high-efficiency laser assisted hydrogen ion (H-) beam stripping was successfully carried out in the Spallation Neutron Source (SNS) accelerator. The experiment was not only an important step toward foil-less H- stripping for charge exchange injection, it also served as a first example of using megawatt ultraviolet (UV) laser in an operational high power proton accelerator facility. This talk reports the design, implementation, and commissioning results of the macropulse laser system, laser transport line, and laser operation for the laser stripping experiment. The macropulse laser consists of a mode-locked picosecond pulsed seed laser and a burst-mode Nd:YAG laser amplifier. The general design concept can be adapted to any temporal beam structures in most accelerators. We have achieved UV pulses with the pulse widths varying between 34 to 54 ps and a maximum peak power over 3.5 MW. A laser transport line is installed to deliver the UV beam to the laser stripping chamber at a transmission efficiency of 70%. Laser operation including remote control and monitor of laser parameters will be described.

Liu, Yun↗

Commissioning and operation of the horizontal test apparatus at SNS

The Spallation Neutron Source (SNS) at Oak Ridge National Lab (ORNL) has built, commissioned and operated a Horizontal Test Apparatus (HTA) vessel in the Radiofrequency Test Facility (RFTF) test cave. It can be operated at 4.5 K using the independent Cryogenic Test Facility (CTF). The HTA is designed to be a single cavity version of an SNS cryomodule with the ability to demount and replace the cavity. It provides the functionality for testing a single dressed SNS medium or high beta Superconducting Radiofrequency (SRF) cavity. The HTA is currently being used in support of R&D for in-situ plasma processing of the cavity's inner niobium surface. The design and commissioning of the HTA at 4.5 K will be presented as well as results from operating the HTA including cool-down, warm-up and steady state operations. Results from plasma processing a warm SCRF cavity in-between cold HTA tests will also be reported.

Kim, Sang-Ho↗

Calculations vs. Measurements for Remnant Dose Rates from SNS Spent Structures

The Spallation Neutron Source (SNS) in Oak Ridge, Tennessee, is an accelerator driven neutron scattering facility for materials research. Presently SNS is capable to operate at 1.4 MW proton beam power incident on a mercury target with a proton beam energy of 1 GeV and 60 Hz repetition rate. SNS target system components are periodically replaced because they reach their end-of-life due to radiation induced material damage. Target vessel, which houses mercury target, is exchanged about two-three times per year and the proton beam window (PBW) is exchanged every two – three years.Each spent structure that leaves the SNS site requires supporting documentation with radionuclide inventory and dose rate prediction for the time of the transportation. Neutronics analyses are performed, assuming realistic irradiation history and decay case to ensure that the container/package, housing the structure, is compliant with the waste management regulations. Analyses are complex due to geometry, multi-code usage and following data treatment.To validate analyses, measurements of dose rates from the spent target vessel # 13 and PBW module #5 were performed. Neutronics analyses were performed to calculate residual dose rates from both structures for the time of measurements.

Popova, Irina I.↗

Analyses to support waste disposition of SNS Inner Reflector Plug

The Spallation Neutron Source Inner Reflector Plug (IRP) is scheduled for replacement. It reached end of life-time because of moderator neutron poison and decoupler burn-out, which is used for shaping neutron pulses. The replacement of IRP is a complex task due to its location in the area receiving high irradiation, being under significant amount of shielding, and size, which requires removal in segments. In order to support the disposal of spent IRP, waste characterization analyses are performed. These analyses include an accurate estimate of the radionuclide inventory and the residual dose rate. Using this data, the package class is determined for the and appropriate containers for temporary storage and subsequent transport are assigned. Analyses are performed in four steps: a radiation transport analysis of the radiation environment for producing the flux and isotope production information using MCNPX, a multi-cell transmutation analysis based n CINDER90, the generation of decay gamma source terms, and the gamma transport analyses of the decay gammas arriving at residual dose rates again using MCNPX. . Due to the complexity of the geometry of the lower segment, transport analyses for the residual dose rate require elaborate work for the source terms definition.

Popova, Irina I.↗

Calculating Residual Dose in Mu2e DS Hall

The Mu2e experiment at Fermilab is a project designed to measure the neutrinoless conversion of muons into electrons. In this experiment there will be particle beams accelerated to relativistic energies impinging upon targets, producing fluxes of secondary particles. It’s among these fluxes where there are substantial fractions of high-energy stable particles arising in spallation and fragmentation reactions, leading to nuclear transmutations in the structural materials surrounding those targets. As a result of neutron activation of the walls and other materials, the structures become radioactive even after the beam has been turned off. This leads to the desire of quantifying the severity of this radiation hazard in order to comply with Fermilab radiological standards.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Investigating the Electromechanical Response Mechanism of Ionic Block Copolymers

One of the rapidly developing frontiers in research and engineering applications is focused on the rational design of materials that have targeted functionalities and tunable responses to external stimuli. Such materials stand to revolutionize how structural components are designed for applications including flexible electronics, biomimetic devices, nanofluidics, as well as separation chemistry. A chief obstacle to achieving this capability is the lack of a fundamental understanding of how chemical structure and morphology give rise to macromolecular properties. With this in mind, our research explores how polymer structure, counterion species, and film morphology affects the electromechanical response of materials when exposed to external electric fields. While the actuating behavior of materials such as Nafion have been commonly investigated, the literature lacks a thorough understanding of how the aforementioned factors drive the electrostatic and mechanical stresses that result in material deformation. Our research has investigated how thin film morphology and counterion species affect the electromechanical response of diblock copolymers containing charged imidazolium groups using neutron reflectometry. The sensitivity of neutron reflectometry to scattering length density as well as sub-nanometer changes in thickness make it an ideal tool for investigating polymer and counterion mobility under applied fields. To this end, we have designed a vacuum chamber capable of applying electric fields to thin films during reflectometry measurements. This chamber was used at the liquids reflectometer (BL-4B) at the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL) to explore the electromechanical response of ionic block copolymers.

Dugger, Jason W.↗

MONTE CARLO NEUTRONICS ANALYSIS OF THE SNS STS MONOLITH

Neutronics analysis for the Oak Ridge National Laboratory Spallation Neutron Source second target station monolith conceptual design was performed entirely with the Monte Carlo method. It has been demonstrated that even though the monolith provides ~peta-scale attenuation of the dose rates, Monte Carlo simulations are within reach of computing capabilities of relatively inexpensive Linux clusters. Several monolith configurations achieved or exceeded design requirements and provide basis for the final design.

Remec, Igor↗

6D Phase Space Measurement of Low Energy, High Intensity Hadron Beam

The goal of this project is to demonstrate a method for measuring the full 6D phase space of an low energy, high intensity hadron beam. This is done by combining 4D emittance measurement techniques along with dispersion measurement and a beam shape monitor to provide the energy and phase space components. The measurement will be performed on new Beam Testing Facility (BTF) at the Spallation Neutron Source (SNS), a 2.5 MeV functional duplicate of the SNS accelerator front end.

Cathey, Brandon↗

6D Phase Space Measurement of Low Energy, High Intensity Hadron Beam

The goal of this experiment is to measure the full 6D phase space of a low energy, high intensity hadron beam. We use 4D emittance measurement techniques for the transverse plane combined with dispersion measurement and a beam shape monitor to provide the longitudinal phase space. The Beam Testing Facility (BTF) at the Spallation Neutron Source (SNS), a 2.5 MeV functional duplicate front end of the SNS accelerator is being used to facilitate the measurement. Early 6D measurements will be presented.

Cathey, Brandon↗

Technical Workings of the 6D Phase Measurement at SNS

The Beam Test Facility (BTF) is a functional duplicate of the Spallation Neutron Source (SNS) frontend with a 2.5 MeV beam on which the first six-dimensional phase space measurement has been completed. This presentation will show the technical underpinnings involved in performing the 6D scan with the BTF. The first part will examine the diagnostic setup involving apertures, a screen, and a bunch shape monitor and how the integrated system functions. The next part will cover the scan logic used in the software. The last part will briefly discuss ongoing efforts to analyze 6D measurements and identify correlations.

Cathey, Brandon↗

DOSE RATE VERIFICATION FOR SNS SPENT STRUCTURES

Residual dose rate measurements were conducted on two Spallation Neutron Source spent structures, target vessel #13 and proton beam window #5, after extraction from their service locations. These measurements were used to verify calculation methods for radionuclide inventory assessment that are typically performed for nuclear waste characterization and transportation. Neutronics analyses for predicting residual dose rates were carried out using complex and rigorous geometric models of the structures and their surroundings. Calculational results were analyzed and compared to the measured dose rates

Popova, Irina I.↗