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At least 1,045 records · Page 58

Plasma Processing of SRF Cavities for the Next Generation of Particle Accelerators

What are the major goals of the project? Goal 1: Optimize interactively processing of the single-cell cavity by combining plasma treatment and vertical cold bath testing. Continue using single cell cavity as the test bed for new applications. Goal 2: Work on upgrading the plasma etching technology for multi-cell SRF cavities. Goal 3: Develop and adapt discharge configurations to critical cavity regions including the electron beam weld (EBW) and iris areas. Goal 4: Develop tailored methods to prepare surface properties for a specific function prior to any additional modification, such as (but not limited to) surface passivation in preparation of other superconducting materials and structures.

43 PARTICLE ACCELERATORS↗

Diagnosing Field Strengths and Plasma Conditions in Magnetically Insulated Transmission Lines Using Active Dopant Spectroscopy

Experimental validation data is needed to inform simulations of large pulsed power devices which are in development to understand and improve existing accelerators and inform future pulsed power capabilities. Using current spectroscopic techniques on the Z-machine, we have been unable to reliably diagnose plasma conditions and electric and magnetic fields within power flow regions. Laser ablation of a material produces a low density plasma, resulting in narrow spectroscopic line widths. By introducing a laser ablated plasma to the anode cathode gap of the Mykonos accelerator, we can monitor how the line shapes change due the current pulse by comparing these line shapes to spectral measurements taken without power flow. In this report we show several examples of measurements conducted on Mykonos on various dopant materials. We also show a negligible effect on power flow due to the presence of the ablation plasma for a range of parameters.

43 PARTICLE ACCELERATORS↗

New Septum Dump Quadrupole Magnet Design

The purpose of the septum dump quadrupole (SDQ) magnet is to expand the beam size on the septum dump of the DARHT Axis 2 downstream transport in the same manner as the S2 magnet expands the beam on the beam stop for mode 1 operations of DARHT Axis 2. This is necessary in order to minimize the heating of the carbon beam dump and suppress desorption of ions. Initially, ions are generated through stimulated desorption and ionization of the monolayers of water vapor stuck to the beam dump surface. These ions propagate upstream at high speeds and act as an electrostatic focusing lens by reducing the beam space charge. As the beam size on the dump decreases, the dump is sufficiently heated so that a surface plasma is formed and much greater quantities of ions are generated through space charge limited emission. The interaction of these ions with the beam causes significant disruption of the beam.

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Design of the New DARHT X-ray and Neutron Shielding and Measured Results

The DARHT Weather Enclosure (WE) project provided an excellent opportunity to redesign and rebuild some of DARHT systems without introducing interruptions to normal operations. Multiple improvements were made to the facility to improve data quality and operational reliability.

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High Average Power RF Window with Improved Multipactor Coating

Multipactor emission can be a serious issue for vacuum electron devices operating at megawatt power levels. It can lead to catastrophic failure from surface arcs or excessive heating of ceramic windows. Titanium nitride is effective at suppressing multipactor emission; however, sputter coating is not strongly bonded to surfaces and issue related to lifetime have arisen. It’s difficult to ensure a uniform coating over large surfaces. This research investigated atomic layer deposition (ALD) as an improved alternative to sputtered coatings. Test windows were fabricated and coated with TiN using ALD, then tested for RF loss and secondary emission. All ALD samples showed RF loss less than 0.01dB with secondary emission yield equal to or better than reported measurements with sputter coated windows. The program also designed a preliminary ALD system capable of coating windows up to 24 inches in diameter.

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IER 501: Pulsed Neutron Die-Away Experiments at LLNL [Slides]

Pulsed neutron die away experiments occur as follows: (1) a pulse of neutrons is injected into a target material via a D-T neutron generator, (2) neutrons thermalize, (3) neutrons spatially equilibrate, and (4) exponential decay is measured in fundamental mode.

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ORNL Neutron Cross Section Measurements of 90 Zr NCSP ND-1 Task [Slides]

Luiz Leal's idea to integrate the experimental uncertainties, covariances, and sensitivities in this workflow and centralize the process at one location led to the creation of a cohesive tool for data testing. It has been practiced for more than two decades by the NCS and ND groups at ORNL. The development and use of the ORNL codes TSUNAMI and TSURFER within SCALE made it possible. Today, it has been extended to SAMINT which enables the coupling of differential and integral data evaluation in a continuous-energy framework.

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RFQ Beam Loss and Shielding Consideration

The proposed novel RFQ-based injector for LANSCE operation includes two independent low energy transports merging beams at the entrance of a single RFQ, which accelerates simultaneously both protons and H- ions with multiple flavors of the beams. One of the design issues of the project is the estimation of shielding requirements for the injector. Continuous access to the injector components reduces the number of times required to open the linac tunnel and saves time for the operation. Estimation involves the evaluation of radiation generated by beam losses in the injector. In this paper, we present an overview of the shielding in existing RFQ injectors and discuss the aspects of shielding configuration for the LANSCE RFQ-based injector.

43 PARTICLE ACCELERATORS↗

Second Target Station High-Fidelity Target Activation Comparison

The development of the Second Target Station (STS) target system at the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL) is well underway. The target system at STS consists of a rotating target disk that contains 21 segments of tungsten clad in tantalum clad in steel. A key aspect of the design of the target system is to account for the delayed heating and material damage caused by the delayed dose from decaying radionuclides. These radionuclides are a product of either spallation reactions or transmutation of the nuclei in the target system. These radionuclides build up in the target system components over the lifetime of the facility, and the radiation that is emitted can deposit energy in the components causing significant component heating and material damage. Monte Carlo N-Particle (MCNP) Version 6.2 transports the various particle species and calculates the spallation products and neutron fluxes throughout the target system. These spallation products and neutron fluxes along with the material definition of each component are relayed to the CINDER2008 transmutation code to calculate the radionuclide inventories and the corresponding decay gamma emission spectra. MCNP6.2 coupled with CINDER2008 is the computational method-of-choice for the analysis discussed in the following sections of this report. The analysis focuses on validating major assumptions in calculating the radionuclide inventory in the STS target system: all of the target segments are fresh, unirradiated material when the protons are incident on the segment, the average of the 21 segments of the target is sufficient to represent a single segment, and that averaging the proton pulse structure over time does not significantly affect the radionuclide inventory. The position-averaged, high-fidelity, and single-tally computational methods are used to validate the assumptions and provide a point of comparison to evaluate how the assumptions impact the radionuclide inventories. A more detailed explanation of the three computational methods is provided in Section 2. The position-averaged and single-tally methods are less computationally expensive when compared with the high-fidelity method where 54,000 individual calculations are needed to calculate 1 hr of STS operation. Section 3 details the comparison of the three methods to show that the assumptions made in the position-averaged method do not significantly impact the radionuclide inventory after 1 hr of operation. The discussions and results in this report are for 1 hr of operation. Due to the computational cost associated with calculating the transmutation and activation using the high-fidelity method, only 1 hr of operation has been calculated. The discrepancies observed after 1 hr of operation are not extrapolated out to longer operational times, and this report does not address how the discrepancies between the computational methods may manifest for longer operational periods.

43 PARTICLE ACCELERATORS↗

Development of Low-Power H - Proton Beam Capability in Area-A

A low-power proton beam capability in Area-A will support NNSA, LANL, Global Security, DoD, and Office of Science missions. It will also provide a stepping-stone towards other future uses of Area-A. We propose a cost-effective technical approach to achieve this goal. The main focus of this project will be to provide beam for a radiation effect beamline and a second pRad beamline.

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