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Survey Draft

A procedure is described and methods which yield toward alignment of positions of all CBETA components within their tolerances. Major principles governing survey and alignment measurement space are briefly shown and their relationship to a lattice coordinate system. Then a discussion of the activities involved in a step-by-step sequence from initial layout to final alignment is described. In the vertical plane, the curvature of the earth does not need to be considered as the dimensions of the whole CBETA project are to small, The leveling is done with respect to gravity.

43 PARTICLE ACCELERATORS↗

Low-noise, radiation tolerant SiCpms

Over the last 10 years, our R&D effort has resulted in a steady progress on improving Geiger detector array technology performance, verifying their reliability and developing three cell layout libraries containing more than 2200 primitive cells for Si and SiC Geiger based single-photon detectors and silicon ROIC array fabrication. Awards from DOE, NASA and DOD, as wells as commercial R&D orders supported much progress, relevant to this program. The expertise gained and the technologies developed or qualified during these programs provided the design database and expertise to carry out the development of this new SiC photomultiplier (SiCpm) technology, successful fabrication of SiCpm detectors, and evaluation of their radiation hardness. After irradiation with protons and neutrons at 1015cm-2 and 1014cm-2 respectively, SiCpms proved radiation hardness, exceeding the expected radiation tolerance The defects induced by irradiation were mainly point defects. A new improved DLTS method (fDLTS – full wave DLTS) hardware and data processing software specific to investigating radiation damage in SiC was developed. Further work is needed to better characterize and control defects induced by charged particles. We recommend further funding of radiation hardened technology development and validation; qualification of device-specific characterization methods like f-DLTS, development of more methods to evaluate defects in SiC, more active involvement of the national labs in evaluating the SiCpm devices, and DOE support of technology transfer to a qualified foundry.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Accident Scenarios for IOTA Ring and Dose Distributions Calculated with MARS15 Code

The Integrable Optics Test Accelerator (IOTA) at Fermilab’s Accelerator Science and Technology (FAST) facility [1] is a storage ring for advanced high intensity beam physics research. Layout of the ring is shown in Fig. 1. A plan view of the ring with enclosure walls are shown in Fig. 2. The entire beam, stored in the IOTA ring, is assumed to be completely lost at either of the three locations shown in Fig. 2. Therefore, we will consider three separate corresponding accident scenarios. The maximal amount of electrons stored in the IOTA ring is estimated to be 2×10 10 electrons with energy of 150 MeV. At locations 1 and 2 the beam is lost on 60-deg dipole walls, while at location 3 the beam is lost on Lambertson magnet wall.

43 PARTICLE ACCELERATORS↗

Parameters and Tolerances for the Booster Dipole Power Supplies

In this technical note we discuss the parameters and tolerances for the booster dipole power supplies. We first discuss the requirements on the current ramp profile for the cases of energy ramps at 1 and 2 Hz. Then we determine the voltage waveforms that correspond to these current ramps. Using the booster magnet lattice and the actual power supply circuit layouts we then calculate the orbit distortion and tune spread caused by the magnetic field amplitude errors in the combined-function dipole magnets at the time of injection and extraction and establish the requirements on the value of the magnetic field amplitude errors at these points along the ramp. We then conclude the note by translating these requirements into the amplitude and time tolerances for the dipole power supplies.

42 ENGINEERING↗

Comparison of conventional vs. modular hydrogen refueling stations, and on-site production vs. delivery

To meet the needs of public and private stakeholders involved in the development, construction, and operation of hydrogen fueling stations needed to support the widespread roll-out of hydrogen fuel cell electric vehicles, this work presents publicly available station templates and analyses. These 'Reference Stations' help reduce the cost and speed the deployment of hydrogen stations by providing a common baseline with which to start a design, enable quick assessment of potential sites for a hydrogen station, identify contributors to poor economics, and suggest areas of research. This work presents layouts, bills of materials, piping and instrumentation diagrams, and detailed analyses of five new station designs. In the near term, delivered hydrogen results in a lower cost of hydrogen compared to on-site production via steam methane reforming or electrolysis, although the on-site production methods have other advantages. Modular station concepts including on-site production can reduce lot sizes from conventional assemble-on-site stations.

08 HYDROGEN↗

Building 1090 Boil-Off Exhaust Modifications 90% Basis of Design

This document provides analysis and proposed modifications to correct current issues at Building 1090. Electrical modifications will add additional emergency Iighting in Labs 170, 174, 178, 182, 184, 186, and 190, and back-up power for the exhaust systems, fume hood lighting and exhaust system controls during a power outage. Mechanical modifications will address building pressurization between the lab and office areas, and replacement of corroded exhaust ductwork and fume hoods related to boil-off operations of corrosive chemicals. Mechanical modifications include the installation of a dedicated, chemical boil-off exhaust fan and ductwork to support corrosive boil-off operations in Lab 184. It should be noted that the proposed solution increases the overall building exhaust demand, also increasing the supply air needed. Electrical modifications include the installation of an uninterruptible power supply (UPS) to provide power to the exhaust fan, controls, and fume hoods to allow safe exit from Laboratory 186 during a power outage. The existing lighting inverter will also be replaced with a larger model to support additional emergency lighting within the labs. Architectural modifications include exterior doors on the east wall of the IDR room. An additional door in the corridor west of Lab 184 will provide direct access to Lab 186 without entering a common building corridor. Lab casework will be modified as-required to accommodate the new layout.

42 ENGINEERING↗

Zeptocalorimetry

Here we present the development of a Zeptocalorimeter. The motivation for designing and implementing such a device is driven, ultimately, by its anticipated exceptional sensitivity (10-21 J/K, at 2K). Such a device would be highly valuable in detecting minute quantities of mass for threat detection, studying fundamental phonon physics, and detecting energetic dissipation events at the attojoule level. To date, the most sensitive calorimeter demonstrated in the literature at 2K has been developed by the Roukes group at Caltech, where they achieved an addendum heat capacity of 10 -15 J/K with a 1/1000 sensitivity to external stimuli. To obtain such a low value of heat capacity requires a very small thermal mass, and thus, one of the greatest challenges in this project is the fabrication of this device, which requires numerous precision nanofabrication techniques. Furthermore, the heat capacity measurement of this device, as performed from room temperature to cryogenic temperatures, is equally challenging, as the transient signals used to determine the platform's thermal time constant require careful attention to the mitigation of feedthrough capacitance and delicate amplifier offsets. In this report we describe in detail the fabrication process flow for developing the calorimeter, including the layout and device design for obtaining a single lumped RC thermal resistance and capacitance, so that the device can be used for quantitative measurements of nanoscale materials with a suitable thermal link. The measurement method and experimental setup are also given, where we explain the heater and thermometer calibration methods, the thermal resistance measurements, the transient measurements, and lastly the cryogenic setup with intermediate frequency cabling and the thermal sinking of those lines.

47 OTHER INSTRUMENTATION↗

High Power S-Band Vacuum Dry Loads for SLAC Linac

In the beginning of LCLS-1 commission era, an unstable termination mode of the residual RF power on all vacuum dry loads of the SLAC linac was found. The S-Band loads on the current SLAC linac RF system were designed, in some cases, 50+ years ago to terminate stably only 2-3 MW peak power into a thin layer of coated Kanthal material as the high power absorber. The technology of the load design was based on a old flame-sprayed Kanthal wire method onto a base material. During SLAC linac upgrades, the RF power sources dramatically increased from 24 MW peak klystrons to 240 MW peak (with new klystrons and SLED cavities). As a result, the residual RF power on the loads was increased accordingly. The original RF loads were overstressed and cannot stably terminate the residual RF power in the present RF linac layout.

43 PARTICLE ACCELERATORS↗

Captain Electronics Technical Report

This report details the current layout of the electronics for the mini-CAPTAIN detector system, as well as the lessons learned during commissioning. We will present some electronics suggestions for future LArTPC systems. Mini-CAPTAIN is one of three detectors used in the Cryogenic Apparatus for Precision Tests of Argon Interactions with Neutrino (CAPTAIN) project at Los Alamos National Lab (LANL). The detector uses many of the same electronic components as current and developing LArTPC experiments. This includes the motherboards, service cards, amplifiers and ADC made by Brookhaven National Laboratory (BNL) and the front-end modules (FEM) made by Nevis Labs. The cold electronics performed well in both vacuum and cryogenic environments after months of exposure. Mini-CAPTAIN was tested with two liquid nitrogen and three liquid argon run cycles. The final testing was performed at the Weapons Neutron Research (WNR) facility at LANSCE. Mini-CAPTAIN was able to maintain a clean electrical signal through most of the test cycles. Most noise reduction was achieved with power source filtering and careful attention to the ground configuration. Direct oscilloscope probing on the front-end output provided the fastest analysis and correction of noise sources. Ground path assumptions and integrity were verified with frequent impedance checks. A high voltage break down event damaged some of the channels on the motherboards and a number of the wire decoupling capacitors. This temporarily introduced significant noise on the wire planes due to current leakage. The detector was taken apart and reassembled three times, with successful noise reduction after each activity. The current raw signal-to-noise ratio is 9 to 1.

42 ENGINEERING↗

Field Demonstration of The Krauklis Seismic Wave In A Novel Mva Method For Geologic CO 2 Storage

The Energy & Environmental Research Center (EERC) conducted a feasibility study of a new, low-impact geophysics monitoring method designed to incrementally track the saturation front of CO 2 injected into a reservoir. The method leverages a new way of transmitting energy from the surface to the reservoir and employs a new subsurface signal called the Krauklis wave (K-wave) and other guided waves for seismic monitoring. The EERC partnered with Seismos, Inc., the company that holds the exclusive technology license for this method, to advance development of K-wave technology, and Denbury Onshore, LLC, to field-test the system. The system was field-tested at Denbury’s Bell Creek oil field, currently undergoing CO 2 -based enhanced oil recovery (EOR) in southeastern Montana. The K-wave system uses a wellhead-mounted source to propagate energy down the wellbore in the form of a tube wave and through the well perforations into the reservoir. Part of the energy transmitted through the perforations into the reservoir converts to slow moving K-waves and/or other guided waves that are expected to propagate through the formation to neighboring wells. The propagated signal would induce tube waves in the neighboring wells that return to the surface to be recorded with a wellhead-mounted receiver. The propagation time of the signal is directly affected by the presence of CO 2 between the wells, so the difference in transit time of the returning signal between pre- and postinjection data sets could be used to help define the lateral extent of a CO 2 saturation front. Objectives of the study were to demonstrate, validate, and evaluate the K-wave method’s ability to monitor the morphology of injected CO 2 and estimate saturation distribution. Results from the demonstration were to be compared to conventional 4-D surface seismic methods, dynamic reservoir simulations, and CO 2 breakthrough data to validate the technology and provide useful information that may result in improvements. Prior to mobilizing for the full-scale K-wave baseline survey, a field test was conducted to better understand wellhead hardware configurations and test the response from the Bell Creek reservoir using three wells. Useful operational information resulted but signal from the first-generation gas release/gas injection source was not recorded in neighboring wells. After the initial field test, numerical modeling of the K-wave method was initiated using parameters specific to the Bell Creek Field. Modeling results indicated that the fundamental concepts behind the K-wave method exhibited problems and revealed a significantly greater attenuation of the signal at the wellbore perforations than expected, totaling on the order of 10-8 from source well to receiver well over a 400-m well spacing. Modeling also showed that greater source frequency bandwidth was needed to produce guided waves within a 30-foot-thick reservoir layer such as that at Bell Creek and that reservoir layer seismic velocity would need to be slower than the velocities of the bounding layers in order to act as a wave guide opposite to what exists at Bell Creek. Modeling results prompted a second field test with a stronger, second-generation displacement source developed in the interim. Concurrent with the second field test, a 3-D seismic survey was acquired to serve as a baseline for project validation and to serve as a monitor data set for the portion of the project area where CO 2 injection had already commenced. The new source was tested using a four-well geometry and failed to produce a detectable signal, which appeared to confirm modeling results and indicated that the Bell Creek Field is not an ideal site for the K-wave test. It was concluded that a source with sufficient strength and bandwidth could not be built to overcome the factors discovered by the modeling within a reasonable amount of time. Several other sites undergoing CO 2 -based EOR were also evaluated; however, none of these sites was amenable because of geology, limitations of source and receiver hardware, or the advanced state of the CO 2 flood. In addition, two other configurations of the source and receiver layout were considered; however, these design modifications either changed the scope of the project or did not meet the goals of the Carbon Storage Program. In consultation with the U.S. Department of Energy (DOE) Project Manager and Technology Manager, a no-go decision was invoked to forego additional expenditures as the technology would not meet current project objectives. Project activities to date have moved the technology forward by developing modeling equations that can be applied elsewhere, advanced the state of wellhead sensors and sources, and spurred improvements to field operations. The 3-D seismic survey in the project area and the dynamic reservoir simulations done as part of this study have provided value for ongoing and future synergistic activities at Bell Creek related to DOE carbon storage goals.

54 ENVIRONMENTAL SCIENCES↗

Experimental Study of the Rare Neutral-Kaon Decays at J-PARC (Final Technical Report)

Understanding the origin of CP violation is currently one of the most forefront issues in elementary particle physics. Together with a better understanding of quark mixing and neutrino mixing phenomena, it is one of the central goals of particle physics, and has been pursued vigorously in many experiments. The very rare decay $K_L \to \pi ^0 v\bar{v}$ provides one of the best probes for understanding the original of CP violation in the quark sector. Particularly, theoretical uncertainties are very small in the Standard Model (SM) calculations, and the value therefore most suitable to be tested for beyond SM contributions. J-PARC E14 (also known as KOTO) aims to reach Standard Model sensitivity and beyond with Stage-1 and Stage-2. KOTO acquired 100 hours beam data in May 2013 and the result has been accepted for publication. From 2015-16, KOTO increased the data set by a factor of twenty, which will allow a limit to be set at the Grossman-Nir bound. This bound is valid in virtually any extension of the Standard Model. By comparing this model-independent bound and SM prediction, it is clear that there is considerable room for new physics. Analysis on these collected data sets shows neutron interactions which mimic the two-photon signal could become a potential background. To discriminate neutron background from the photon signal, one important tool, as shown in current data, is to perform detailed waveform analysis of the signal from the phototubes. To fully capture the calorimeter pulse shape with best fidelity from 100 out of the 2700 channels of CsI, we built the 500 MSPS (Mega Samples Per Second) with 14-bit digitizers. With KOTO Stage-2 currently in the planning stages, we started R&D work on a full width, but length scalable photon veto barrel detector with detailed layout of active detector elements.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

21-ID ESM Beamline Radiation Shielding Analysis

The radiation shielding analysis of Electron Spectro-Microscopy (ESM, 21ID) at 500 mA is documented in this technical note, including Gas Bremsstrahlung (GB) and Synchrotron Radiation (SR). Figure 1 shows the layout of ESM beam line, which uses 2 undulators (EPU105 or EPU57).

36 MATERIALS SCIENCE↗

Proposed NRCDA Groundwater Pathway Conceptual Model

As requested by Solid Waste Management (SWM), this report documents the Savannah River National Laboratory’s (SRNL’s) evaluation of updated Naval Reactor waste container and inventory projections and proposes a Naval Reactor Component Disposal Area (NRCDA) groundwater (GW) pathway modeling approach for the next E-Area Low-Level Waste Facility (LLWF) Performance Assessment (PA). Two areas within the E-Area LLWF are used as disposal sites for reactor components from the U.S. Navy. Currently, components arrive by rail and are moved by crane to the 643-26E at-grade gravel disposal pad. Prior to operational closure, reactor components were stored and ultimately disposed in-place on the 643-7E NRCDA (Wilhite and Flach 2004). Naval Reactor (NR) waste is comprised of highly radioactive components consisting of activated corrosion-resistant metal alloy contained within welded thick steel casks, and auxiliary equipment primarily contaminated with Activated Corrosion Products (sometimes referred to as “crud” by the U.S. Navy) at low levels and contained within thinner-walled bolted containers. The 643-7E disposal pad, which contains 41 casks and has an interim soil cover, is closed to future receipts. The latest NR waste projections for the 643-26E disposal pad are substantially different from the original estimates due to a change in reactor maintenance. The original estimate was for 50 heavily shielded, welded casks and 50 thinner-walled bolted containers (primarily shield blocks). Currently, NR Programs project 33 heavily shielded, welded casks, of which 31 are already in-place on the 643-26E pad, and 381 thinner-walled bolted containers. In addition to new waste form projections, there have been changes in facility layout and closure plans as well as PA modeling improvements. This report documents these changes as well as key NRCDA recommendations from the 2015 PA Strategic Plan (Butcher 2016).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Design and Characterization of High Thermal Conductivity Pipes from Roll-to- Roll Processed Hybrid Copper-Polymer Strips for Waste Heat Recovery

Metal based heat exchangers targeting low temperature (<150°C) waste heat recovery (WHR) face high maintenance and material costs [1] that result in long payback periods (>1 year). Low-cost polymer pipes suffer from poor thermal conductivity (~0.2 W/m.K), and thus a low overall heat transfer coefficient. Previous reports demonstrated thermal conductivity enhancement in polymers through systematic molecular alignment [2, 3, 4], or by metal micro-particle inclusions [5]. However, these approaches suffer from scalability issues for WHR heat exchangers in terms of cost [1, 3], and thermomechanical considerations [6, 7]. In this work, we propose hybrid metal-polymer strips that are strategically designed to enhance thermal conductivity by cladding copper around polymer strips. The polymer strips with copper-clad edges are wound helically to form the pipes for a heat exchanger. Through numerical simulations, we optimize the copper-polymer strip layouts to achieve high wall thermal conductivity (k > 1 W/m.K) and also have low volume fraction of copper (<70%) for the composite pipes. In copper-polymer composite heat exchangers, the bottlenecks for heat transfer are the thermal interfacial resistances of copper-copper and copper-polymer joints. We experimentally measured interfacial resistances to be ~1x10 -5 K.m 2 /W and ~4x10 -5 K.m 2 /W for copper-copper and copper-polymer joints, respectively. Using the measured interfacial resistances, we further optimized the design of the hybrid pipes to find high thermal conductivity (> 1 W/m.K) designs. We predict up to ~20 % enhancement in overall heat transfer relative to an all polymer (k = 0.2 W/m.K) heat exchanger system. Using a cohesive zone modelling (CZM) for predicting delamination at the weld joints, we find that our hybrid pipes can have operating internal pressures > 200 psi. The optimized designs of hybrid metal-polymer pipes provide a scalable and cost- effective means for harvesting waste heat from low temperature sources. Thekdi, A., and Nimbalkar, S. Oak Ridge National Lab (2014). Shen, Sheng, et al. Nature nanotechnology 5.4 (2010). Xu, Yanfei, et al. Science advances 4.3 (2018). Smith et al. ACS nano, 9(2), (2015). Sofian, N.M., et al., Journal of Thermoplastic Composite Materials (2001). Aymonier et al. Chemistry of Materials, 15(25), (2003). Tavman, I.H., Journal of Applied Polymer Science, 62(12), (1996).

C Rajagopal, Manjunath↗

NSLS-II upgrade proposal with splitting dipole scheme

In this note, a preliminary study of the NSLS-II upgrade lattice with splitting-dipole scheme is presented. The constraints from maintaining the layout of the ring and re-using the existing magnets have been illustrated. The linear and nonlinear beam dynamics are discussed as well.

36 MATERIALS SCIENCE↗

Fuel Fabrication Facility Study for FCF HALEU

Nuclear energy technology developers seek to bring to market new advanced reactor designs and new light water reactor fuel designs, many of which would deploy fuel made from uranium with 235 U enrichment ranging from 5% to 19.75%. There is currently no commercial supply of uranium in this enrichment range, which is higher than used in today’s light water reactors but still lower than the safeguards limit of 20% 235 U. This limitation is a barrier to development of demonstration of these new nuclear energy technologies. As a means to address this near-term need, DOE and Idaho National Laboratory (INL) has considered how the HALEU product from sodium-bonded spent fuel treatment in the INL Fuel Conditioning Facility (FCF), located at the Materials and Fuels Complex (MFC), might be provided and fabricated into some of the new fuel designs. The evaluation presented in this report addresses the potential establishment of two types of fuel fabrication capability at INL, represented generically as a ceramic-type (or pellet-type) fuel fabrication line and a metallic fuel fabrication line. Because the FCF HALEU feedstock contains residual transuranic contamination and a relatively small amount of residual fission products, fabrication with that material is necessarily performed inside of engineered confinement barriers, such as gloveboxes, which would be filled with inert gas for most of the fuel types considered. The throughput rate of the fabrication lines envisioned is 2.5 metric tons of HALEU fuel per year, which is judged to be sufficiently representative of engineering-scale. Space in three existing buildings was identified for consideration in this study of pre-conceptual equipment layouts. The scope and nature of the work needed to prepare each of the three buildings for each type of fuel fabrication was identified (though not in engineering detail), and three-dimensional models of envisioned fabrication equipment were laid out in each of the buildings to assess adequacy of space. The study concluded that either type of fuel fabrication line can feasibly be installed and operated in either of the three buildings. However, each of the three buildings presents different challenges in preparation, due to accommodating current missions that would need to be relocated or necessary decontamination and decommissioning work to free-up space for fuel fabrication, or due to complications of accessibility. Rough order-of-magnitude (ROM) cost estimates for preparing buildings begin at $10M ( 20%/+50%) and would increase with increased complexity of building modifications. The cost of fabrication equipment and gloveboxes is roughly estimated to be $21M (-20%/+50%) for a metallic fuel fabrication line and $27M (-20%/+50%) for a ceramic/intermetallic fuel fabrication line. Nominal operating costs are estimated to be $7M per year (in 2019 dollars), increasing from lower amounts needed as the operating crew is being assembled and trained.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The NSLS-II Alignment Coordinate System Conventions

For NSLS-II construction activities, a construction coordinate system is established with certain connections to geodetic NY State Plane Coordinate System, while physicists design the lattice and layout of accelerator and beam lines in a relatively dependent virtual space with their beam following coordinate system. In engineering design process, mechanical drawing designers, and beam line experts may both have their own coordinate system in a self-convenient manner. This situation will bring out problems of consistency and eventually lead to potential chaos for survey and alignment work. Therefore, it prompts to establish coordinate conventions recognized by all the relevant groups in order to smooth the coordinate processing flow when executing the alignment task according to specific design. Here descriptions about several existing coordinate system will be delineated and the definition of accelerator alignment coordinate system will be emphasized. The rotation and translation mathematical parameters will be given to allow for easy transformation. All the units are in meters. A programming code has been written to deal with a key requirement of integrating components’ fiducials into storage ring coordinate system. The parameters and code can be validated and tested by relevant groups.

36 MATERIALS SCIENCE↗

Online Simulation Tools for Orbit Correction in the CBETA Machine (CBETA Note 029)

Control of beam trajectory is essential in particle accelerators. The trajectory of a beam is sensitive to various types of imperfections that cause it to deviate from its desired path along the accelerator. Orbit correction is hence fundamental for the control of beam trajectory. In this work we aim demonstrate orbit correction using singular value decomposition techniques applied to distorted orbits generated in the CBETA-V Virtual Machine. In particular we present two concrete examples of such correction in different sections of the CBETA Fractional Arc Test layout. Our goal is to construct the backbone of an orbit correction software toolkit to be tested in the CBETA-V Virtual Machine and eventually implemented in the completed CBETA control system.

43 PARTICLE ACCELERATORS↗