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Infrastructure Investments in LAMDA: SEM Mill and Vault (NSUF 2019 Milestone Report)

This document summarizes the procurement, installation, and commissioning of a scanning electron microscope (SEM) mill produced by Fischione Instruments and a lead-shielded vault for specimen storage in support of Nuclear Science User Facility (NSUF) awards for use in Oak Ridge National Laboratory’s (ORNL) Low Activation Materials Development and Analysis (LAMDA) laboratory. The Model 1061 SEM mill is a tabletop ion milling system for advanced sample preparation of high-quality SEM samples. This device was chosen for its broad range of ion energies allowing for both rapid milling and final polishing of the sample surface. The purchase order with Fischione Instruments was released and awarded by ORNL procurement on September 11, 2018. The instrument was shipped in December of 2018 and was installed in the LAMDA laboratory in March of 2019. During the commissioning of this equipment, electron backscatter diffraction (EBSD) was performed on specimens before and after milling to show the enhanced surface quality. With the purchase of a lead vault dedicated to NSUF library materials co-located in the LAMDA laboratory, the NSUF program will be able to maintain a significant sample library in LAMDA. These specimens will be easily accessible for rapid turnaround experiment (RTE) awards and will reduce the overall cost of year-over-year storage and shipments to and from ORNL hot cell facilities. The contract to fabricate a fourth lead vault dedicated to NSUF specimen storage was awarded by ORNL procurement on August 10, 2018. Installation of the new vault was completed in January of 2019.

47 OTHER INSTRUMENTATION↗

Parallel Computing for Massive Dynamic Contingency Analysis

The first step towards running PSLF in a high-performance computing (HPC) environment was porting PSLF to the Linux operating system from the current shipping target of MS Windows. The target machine was the LLNL Quartz system which is a Linux cluster configured for large parallel jobs. It has 2,688 batch nodes with Dual Socket Intel E5-2695 v4 (Broadwell) CPUs with 18 cores each, with a total of 344,064 GB of memory, each node having 128 GB of memory. Nodes are connected with an Intel Omni-Path 100 GB/s interconnect. Quartz runs the Tri-Laboratory Operating System Software (TOSS) that includes Red Hat Enterprise Linux (RHEL) distribution used on the LLNL HPC machines.

24 POWER TRANSMISSION AND DISTRIBUTION↗

Analysis of Material Properties of Aged Rigid Polyurethane Foam

Polyurethane foams are organic materials which can be classified as mechanically rigid or flexible. They are chemically inert, relatively unaffected by the presence of water (cracking, swelling, absorption), and can be manufactured in densities from 3-40 lb/ft 3 . In addition, polyurethane foams have exceptional mechanical and thermal properties, which support use of polyurethane foams in the 9977 shipping packages. These packages are designed for shipment of special nuclear material and are approved for storage in the K-area complex (KAC) at Savannah River Site. Through the analysis of conditioned foams, a service life ofFR-3700 can be estimated for the storage of the 9977 packages. Thus, considering anticipated temperatures of the 9977 packages in the KAC, FR-3700 was conditioned at 160°F, 185°F, 215°F, 250°F, and 160°F with 50% relative humidity, which remains within the service temperature of-320°F - 250°F of the FR-3700 foam in the 9977 packages. Prior studies have analyzed foams after 7, 20, and 30 months of conditioning with the current study analyzing foams up to 55 months of conditioning. Considering the limited information on the effects of radiation on FR-3700, samples were irradiated with a cobalt-60 source at a high and low dose rate of 90.9 krad/hr and 16.67 krad/hr, respectively, to examine the effects of irradiation and dose rate on thermal properties. It was found that foams conditioned up to 55 months had comparable heat capacity values to FR-3700, with a slight increase due to humidity. Results suggest that fire additives began decomposing at higher conditioning temperatures, reducing the average percent mass loss. Overall, irradiation and humidity had minimal effects on thermal properties of FR-3700.

36 MATERIALS SCIENCE↗

Expanding the Photovoltaic Supply Chain in the United States: Opportunities and Challenges

Growth in U.S. manufacturing of solar-grade polysilicon, photovoltaic (PV) cells, and PV modules has not kept pace with global growth in these industries, and in some cases has even decreased. As a result, the United States has lost approximately 80% of its global market share in these industries over the past decade. However, projections of strong PV demand growth continuing in the United States and globally—along with significant announced U.S. cell and module plant expansions—suggest that PV could have important near-term impacts on related U.S. manufacturing sectors. This report primarily considers the infrastructure availability in the United States to meet demand for industries upstream of PV manufacturing if all U.S. PV installations were manufactured domestically from domestically sourced materials and components. It does not evaluate economic factors such as cost-competitiveness with other countries, policy incentives, shipping costs, and so forth, which are important factors to evaluate but are outside the scope of this work. Our goal is to delineate the infrastructure challenges and opportunities that upstream U.S. manufacturing sectors could encounter if the U.S. PV manufacturing sector grows. This analysis could be used in future discussions of the feasibility of creating a domestic PV supply chain that relies on domestic sourcing for upstream materials.

14 SOLAR ENERGY↗

Storage and Transport Cask Data For Used Commercial Nuclear Fuel

This document is a compilation of publicly available information on spent/used nuclear fuel storage and transport casks in use in the United States as of the summer of 2013. As such, it is a functional update and extension of JAI-582, “Shipping and Storage Cask Data For Commercial Spent Nuclear Fuel,” originally published by JAI Corporation in March 2005. This report is intended to provide a convenient reference for those with interest in, or those engaged in the production, handling, storage, transport, and disposition of spent/used commercial nuclear fuel. Data for each cask is tabulated in a standardized table format to facilitate rapid access to key design and performance information, and to enable the document user to more rapidly conduct comparative analyses of cask design and performance parameters. Multiple-assembly “canisters,” and both canister-based and non-canistered packages are included in the main body of the report. Packages that have been used in the past, but which are no longer in active use in the U.S., are included in Appendix A.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Saltstone Fourth Quarter Calendar Year 2018 (4QCY18) Toxicity Characteristic Leaching Procedure (TCLP) Results

The aqueous waste from Tank 50 (salt solution) is sampled quarterly for transfers to the Saltstone Production Facility (SPF). Salt solution is treated at SPF and disposed of in the Saltstone Disposal Facility (SDF). A SDF waste form (saltstone) was prepared in the Savannah River National Laboratory (SRNL) from the Tank 50 Waste Acceptance Criteria (WAC) sample and Z-Area premix material for the fourth quarter of calendar year 2018 (4QCY18). Results from this memorandum support Task 2: ‘Grout Leaching Analyses’ of the Task Technical Request (TTR) prepared by Savannah River Remediation (SRR). After a 28 day cure, a sample of the SDF waste form was collected and shipped to a certified laboratory for analysis using the Toxicity Characteristic Leaching Procedure (TCLP). The 4QCY18 saltstone sample met the South Carolina (SC) Code of Regulations for Hazardous Waste Management Regulations (HWMR) 61-79.261.24 and 61-79-268.48 requirements for a non-hazardous waste form with respect to Resource Conservation and Recovery Act (RCRA) metals and Underlying Hazardous Constituents (UHCs), and also met the SPF WAC.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Measurements of fission gas release from nuclear fuel in support of BISON fuel performance analysis

This project established a fuel irradiation and fission gas release (FGR) loop that has been designed for implementation at the PULSTAR reactor of North Carolina State University (NCSU). The FGR loop is capable of analyzing various types of fuel samples including, e.g., uranium dioxide fuel (UO 2 ) and uranium silicide (U 3 Si 2 ) samples. The fuel samples were produced and characterized at Idaho National Laboratory (INL) and shipped NCSU. The samples are ready for irradiation in the FGR loop to a given total thermal neutron fluence and under controlled temperature conditions. An innovative high resolution gamma-ray spectrometry approach and instrumentation have been established to monitor the loop’s sweep gas and perform high accuracy measurements of the gas release rates relative to predicted birth rates to establish the release-to-birth ratio (R/B) for a given radionuclide. In addition, uncertainty minimization is achieved through the formulation of the measurement observables into relative release-to-birth indicators for selected radionuclides. The experimental findings will be utilized to enhance and validate the fission gas release models that are currently implemented in the BISON fuel performance code. The experimentally deduced physical parameters will be incorporated in BISON’s fission gas release models. Atomistic simulations of fuel behavior have been performed to investigate the mechanisms of fission gas migration in the fuel. At this stage, performance of the fuel irradiation experiments awaits licensing approval by the US NRC.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Recovery of Rare Earth Elements from Coal Mining Waste Materials

The objective of this proposed project was to locate coal overburden material that had rare earth elements (REEs) at concentrations of 300 ppm or higher. After securing the feedstock the next goal was to efficiently extract and purify the feedstocks to a purity of greater than 95%. A techno economic analysis was conducted to determine the economic viability of mining and processing REEs associated with Appalachian coal deposits. All aspects of mining, mineral processing, by-product potential, waste management, permitting and economics were examined. Attention was paid to the separation, degree of purification and marketing of Rare Earth elements. Along with REEs we evaluated the economics of the recovery of other metals of interest aong with the REEs. Our site location chosen was at the Jeddo Coal Site near Hazleton, Pennsylvania. The primary site was at the Upper Leigh High Mine. However, that changed to the North Eckley Mine site. We have analyzed a third site that will now be our second alternative to North Eckley. That site is the Highland mine site. This site is in a similar basin as the North Eckley site. During this project we evaluated various acids and extraction conditions. We have settled on using HCl as the acid of choice. One of the advantages of using HCl is it allows for easy removal of the highest contaminating metal, iron. When iron reacts with HCl in the presence of high chlorides it creates the anion complex FeCl 4 -1 . This FeCl 4 -1 complex will bind with an anion exchange resin. Greater than 99.8% of the iron is removed with this technique. Once the FeCl 4 -1 complex is bound to the anion exchange resin it can be released easily by just passing water over it. This water dilutes the FeCl 4 -1 to form FeCl 3 which is not anionic and therefore not attracted to the anion exchange resin. The FeCl 3 solution is a popular water flocculating agent used all over the world for water purification. We plan on this being one of our products produced. One of our goals was to create a multipurpose facility that was capable of handling multiple feedstocks. The proposed multipurpose facility will be able process all coal biproducts and coal products. These include 1.) clays that can easily be leached with ion exchange or acid 2.) Hard mineral deposits that can be leached with high pressure acid digestion 3.) Fly ash can be leached in the high-pressure acid digestion reactor. Fly ash is not a focus of this proposal but, the beneficial aspect of its utilization in this design cannot be overlooked. 4.) Acid Mine Drainage (AMD) Sludge is a high source of REE’s and can easily be dissolved to form a pregnant leach solution. Not shown on this simplified block flow diagram but crucial to its success is the recycle of acids. Our REE separation system is a continuous ion exchange process. The first stage is the separation of the non-REEs from the REEs. This is accomplished because the REEs are relatively larger than most of the non-REEs and typically have higher oxidation states (+3) than the non-REEs. In this step all the elements stick onto the column. However, as the columns are rinsed with various concentrations of acids different elements come off. For example, monovalent elements such as sodium and potassium elute off the column with a 1M HCl solution. Divalent elements such as calcium and magnesium do not elute until a 2M HCl solution is passed over the columns. The trivalent elements (REEs) are not eluted until a much higher concentrated acid is passed of the columns. Iron is also a trivalent, but it was removed in a prior anion exchange system. Aluminum is trivalent too, but it is much smaller than the REE atoms and elutes near the end of the 2 M HCl with the divalents. At the stage 2 and 3 our volume and masses have become too small to run on the continuous system. Therefore, we used a batch chromatography column or a flash chromatography column. The stage 2 process separates these REEs into 3 different fractions. A light, mid and heavy fraction. We calculated that we recovered greater than 90% of the REEs. This third column was packed with a different stationary phase. Five elements were chosen and purified to higher than 95% purity as shown by our internal testing. These elements were shipped to the DOE.

01 COAL, LIGNITE, AND PEAT↗

Radioisotope Power System Dose Estimation Tool (RPS-DET) User Manual

Radioisotope power systems (RPSs) convert decay heat from radioactive materials to electrical power. The National Aeronautics and Space Administration (NASA) uses RPSs for certain orbiters, landers, rovers, and probes that cannot rely on solar or chemical power. Most of the emitted charged particles in RPS fuels are locally absorbed, and the particles’ kinetic energy is converted into thermal energy as they slow down in the surrounding materials. This heat is subsequently converted into electricity through some form of energy conversion process (e.g., thermoelectric, heat engine, thermionic). While nearly all the charged particles are stopped locally, a non-trivial portion of the emitted neutral particles (neutrons and photons) escape the fuel and are free to interact with surrounding materials. This escaping radiation field can be operationally problematic for certain instruments, materials, electronics, etc., and can cause problems during terrestrial shipping, integration, testing for personnel, instrumentation, etc. Furthermore, the fuel’s emission spectrum evolves over time as the parent isotopes decay away and daughter products accumulate. This changing fuel composition alters characteristics of the ambient radiation field over time, which is further affected by RPS orientation and the surrounding environment. Tools that can rapidly estimate the radiation characteristics of RPSs with various fuel compositions, fuel ages, various RPS orientations, and in/on different spaceflight and planetary scenarios provide researchers with an opportunity to quickly estimate the radiation implications of a given RPS scenario. The RPS dose estimation tool (RPS-DET) provides engineers, scientists and analysts who are not trained in the art of particle transport software with a solution for quickly building, simulating, and analyzing the radiation impacts of various RPS designs in relevant spaceflight and terrestrial environments.

30 DIRECT ENERGY CONVERSION↗

Performance Evaluation of the ThermoLift Natural Gas Fired Air Conditioner and Cold-Climate Heat Pump

ThermoLift is currently developing its Thermal Compression Heat Pump (TCHP™), a natural-gas driven air conditioner and cold-climate heat pump, which can provide space heating, water heating, and air conditioning simultaneously in a single device. The system has broad application as a combined heating, ventilation, and air-conditioning (HVAC) solution with the benefit of substantial energy, cost, and greenhouse gas (GHG) reductions. Unlike traditional vapor compression heat-pumps, the TCHP™ uses helium as a working fluid in place of high global warming potential (GWP) refrigerants. The development effort has produced three iterations or generations of prototypes with advancement of the technology readiness level (TRL) from TRL-1 (TCHP™ Gen 1.0) to TRL-5 (TCHP™ Gen 3.0). In August of 2013, the US DOE solicited the submission of proposals through funding opportunity announcement DE-FOA-0000823, Building Technologies Innovations Program. The Office of Energy Efficiency and Renewable Energy (EERE) subsequently accepted ThermoLift’s proposal to develop a heat pump system based on the Hofbauer cycle, a new cycle that supplants the Vuilleumier cycle and provided funding for prototype evaluation at Oak Ridge National Laboratory (ORNL). ORNL is a widely known research center for developing and evaluating building technologies. Through its Building Technologies Research and Integration Center, ORNL has unique capabilities which allows them to collaborate with industry and academia to advance building component technologies. The TCHP™ Gen 3.0 prototype was shipped to ORNL on July 23, 2018. After installation and integration of the heat pump into ORNL’s test facility and performing instrumentation validation and calibration, extended operation of the heat pump was achieved during continuous operation on August 6, 2018, and includes various heating and cooling temperature ranges and performance analysis. The Gen 3.0 prototype was evaluated at four “ambient” temperatures: −25°C, −8.33°C, 8.33°C, and 20°C, (−13°F, 17°F, 47°F, and 68°F) denoted as test points 1-4, respectively. For heating, cycle coefficients of performance (COP) at the four “ambient” temperatures were found to be 1.30, 1.46, 1.52, and 1.61, respectively. Furthermore, there is no capacity reduction as the inlet temperature to the cold heat exchanger (HX) decreases. The heating capacity delivered by the TCHP was found to be 12 kW at -25°C. Finally, this final report identifies measures for obtaining further efficiency improvements.

42 ENGINEERING↗

Low-GWP Refrigerant Evaluation in AC Systems for High Ambient Temperature Applications – Acquire Nortek Residential AC/HP Units for Evaluation and Model the Units Using HPDM

For the upcoming refrigerant transition from HFCs to minorly flammable HFO refrigerants (A2L), refrigerant charge reduction is important to mitigate the fire hazard. Microchannel heat exchangers (MHXs) are a mature technology, which is effective in reducing system charge while maintaining similar heat transfer performance. MHXs will be applied more widely when the new refrigerants are used. Prior studies of the A2L HFO blends were mostly focused on fin-and-tube coils (FTC). An in-depth study for an air conditioner (AC)/heat pump (HP) system using all microchannel heat exchangers is still lacking. In FY19, a side-to-side comparison will be conducted between two residential split heat pumps, one using all FTCs and the other using all MHXs for drop-in investigation, to identify potential issues for future design. The two heat pumps have similar rated capacity, SEER, HSPF levels, similar fan, blower and compressor, but differ in heat exchangers. Both the HPs use two-stage compressors to facilitate investigating different refrigerant flow rates. We will drop-in HFO refrigerants (replacements for R-410A, e.g. R452B, R447B, R32, etc.). The experiments will reveal the potential of MHXs for charge reduction, and how the two systems using A2L refrigerants operate under standard SEER and HSPF rating conditions. The two units were donated by our partner, i.e. Nortek Global HVAC, an industry leader in making heat pumps using all MHXs as well as FTCs. The units were shipped to ORNL this week, and the product design data were also shared for modeling the two units using HPDM.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Regulatory and Licensing Strategy for Microreactor Technology

With electricity demand on the rise, an increase in the use of nuclear energy is needed in order to meet future energy demands. The use of nuclear energy will not only begin to positively address this demand, but will also mitigate the negative impacts of carbon-induced climate change and provide energy security to the United States. An appropriate option to address the increasing energy demand is the use of advanced reactor systems like microreactors. Microreactors, often referred to as special-purpose reactors or vSMRs, are neutronically simple, factory manufacturable, easily transportable, and designed to produce less than 20 MWt (for classification as Hazard Category 2 per 10 CFR 830, DOE STD 1027). These reactors are decentralized energy sources that have the ability to provide sustainable and affordable power to remote communities and to industrial users, while having self-contained geometry that requires very low maintenance care. In order for microreactors to be approved for operation, they must abide by and successfully complete a rigorous regulatory and licensing process monitored by the Nuclear Regulatory Commission (NRC), the Department of Energy (DOE), or the Department of Defense (DoD). Because microreactors are a relatively new and disruptive technology, there is no clear licensing path for them to follow. Current licensing frameworks are tailored specifically to large, traditional light water reactors (LWRs) that have been developed and understood by the nuclear industry for many years. Unlike LWRs, microreactors have major design differences, specifically in the materials, coolant, reflectors and potential technology applications used. They also have higher in-core operating temperatures, which have the potential to push the materials used past their allowable limits. Because they are much smaller, safety margins, the amount of space required for assembly, and the distances required to meet dose-based regulatory criteria can technically be altered to better fit their new size. The following strategies and recommendations are intended to assure that key licensing issues do not influence the path to microreactor development, demonstration, and commercialization: Nuclear Regulatory Commission • The NRC should address the lack of knowledge and support of risk informed decision-making concepts from staff members and continue to advance and communicate risk initiatives using their Risk Informed Steering Committee • More research should be done into whether or not microreactors, which are small Class 103 facilities, can be licensed using Class 104-type guidance (e.g., NUREG 1537) • The NRC should use frequency-consequence curves to incrementally reduce regulatory uncertainty and risk to facilitate future construction and operation of advanced reactor designs Department of Energy • The DOE should continue to implement their multi-step Phenomena Identification and Ranking Table process in order to help detect and recommend the major design and technology work needed for licensing future reactor systems • The DOE should consider a joint licensing approach with the NRC where microreactors first go through the DOE process, then finish with the NRC process, providing an advantage for both applicants and NRC staff Department of Defense • The DoD should invest in personnel with sufficient expertise, incorporate their military reactors into tactical power systems, and self-regulate using Section 91b of the Atomic Energy Act Transportation • Licensees should convert enriched uranium hexafluoride into metal or oxide at an enrichment facility and then transport them to a fabrication facility • To avoid transportation issues altogether, licensees should consider positioning the enrichment and fabrication facilities on the same site • The DOE should provide their support in developing new shipping packages for safe transport, criticality benchmark data needed to license high-assay low-enriched uranium fuel facilities and transport packages, and provide financial and technical help to the Department of Transportation; and, • The NRC should help transportation efforts by finalizing and developing guidance for implementing 10 CFR 73 and 10 CFR 74 specifically for Category 2 Special Nuclear Material.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Economic Analysis of Renewable Fuels for Marine Propulsion

The current global marine fuel consumption is estimated to be around 330 million tonnes annually, and the demand is expected to be doubled by 2030 due to increased global trade. Over 90% of the world's shipped goods travel by marine cargo vessels - one of the largest contributors to emissions of SOx, NOx, and PM. To meet the growing demand and the upcoming more stringent air emission regulations, now is the time to explore alternative fuels to penetrate the marine fuel markets. Biofuels can undoubtedly play an essential role in the future marine fuel that is more renewable, and lower sulfur and emissions. Both techno-economic analysis (TEA) and life cycle analysis (LCA) are effective tools to assess the economic and environmental feasibility of various biofuel pathways, in terms of their market competitiveness and environmental benefits concerning energy savings and air emissions reductions.

09 BIOMASS FUELS↗

LANL Phase 3 Test Plan For Container Loading to Support the Fire-Induced Pressure Response and Failure Characterization of PCV/SCV/3013 Containers

Fire testing of 3013 containers loaded with surrogate materials and water will be conducted to determine the response of 3013 containers stored in K-Area Complex (KAC) to a facility fire. Based on the proposal for the test configuration and loading, the objectives of the fire test are as follows: 1. “To increase understanding about the pressure and temperature conditions at which failure occurs; 2. To determine the allowable moisture for which failure will not occur under specified fire conditions, and 3. To increase understanding regarding the effects of salts on the pressurization, corrosion, and potential failure of the container.” Surrogate materials will be prepared at Los Alamos National Laboratory (LANL) and loaded in the 3013 containers. The containers will then be welded at LANL and shipped to Savannah River Site (SRS) for the installation of fittings and leak testing.

42 ENGINEERING↗

Building Island Resilience through the Energy, Water, Food Nexus

Islands face unique and often exaggerated threats from climate change. Additionally, the very nature of islands creates greater dependence on imported food and energy resources. Extreme events have highlighted weaknesses in island energy, water, and food systems as a result of utility outages and shipping delays. These events have challenged islands to improve their resilience and seek new strategies to ensure energy, water, and food security. One such island is Sint Eustatius, which has constructed a first of its kind solar park providing reliable energy, community agriculture, and harvested rainwater for irrigation This paper highlights integrated strategies to help islands enhance resilience across the energy, water, food nexus.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Saltstone First Quarter Calendar Year 2019 (1QCY19) Toxicity Characterstic Leaching Procedure (TCLP) Results

The aqueous waste from Tank 50 (salt solution) is sampled quarterly for transfers to the Saltstone Production Facility (SPF). Salt solution is treated at SPF and disposed of in the Saltstone Disposal Facility (SDF). A SDF waste form (saltstone) was prepared in the Savannah River National Laboratory (SRNL) from the Tank 50 Waste Acceptance Criteria (WAC) sample and Z-Area premix material for the first quarter of calendar year 2019 (1QCY19). Results from this memorandum support Task 2: ‘Grout Leaching Analyses’ of the Task Technical Request (TTR) prepared by Savannah River Remediation (SRR). After a 28 day cure, a sample of the SDF waste form was collected and shipped to a certified laboratory for analysis using the Toxicity Characteristic Leaching Procedure (TCLP). The 1QCY19 saltstone sample met the South Carolina (SC) Code of Regulations for Hazardous Waste Management Regulations (HWMR) 61-79.261.24 and 61-79-268.48 requirements for a non-hazardous waste form with respect to Resource Conservation and Recovery Act (RCRA) metals and Underlying Hazardous Constituents (UHCs), and also met the SPF WAC.5-7

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Transforming the Uranium Fuel Cycle: Safe & Economical Conversion of DUF 6 to DUF 4 [Slides]

Project Outcomes: Designed and fabricated SS reaction vessels for executing reactions with UF 6 at SIGMA, followed by transport and analysis at TA-48; Established a new capability at SIGMA for performing small mass transfers of UF 6 ; Safety documentation approved for performing new UF 6 chemistry at SIGMA; Staff training and conversion opportunity established for LANL Seaborg post-doc; Neat reaction with HMDS (CH 3 ) 3 Si-Si(CH 3 ) 3 produced fluorosilanes; In reactions with solvents, fluorination observed. No DUF 4 observed yet. Observations: Only 4 reactions were completed – more clearly needed; Due to problems with procurement, we did not get the mass control flow (MFC) unit until late August; Due to staff and time shortages UF 4 was never delivered from SIGMA to TA-48 by SHIP-IT; Established ability for future collaboration between C and Sigma.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Active Measurement of Plasma Parameters in Over-Dense MFE Reactor Plasma Using High Frequency Beat-Wave Resonantly Generated Thermal Bernstein Waves

UC Davis was funded to explore the combination of beat-wave excitation and laser scattering to make completely non-invasive determination of local plasma conditions. This involves the use of two high frequency mm-wave sources of differing frequencies (the pump waves) to excite plasma waves at the difference of the frequencies, which is known as the beat frequency. The difference frequency or the frequency of the beat wave is chosen so that we produce plasma waves whose fluctuating electron density is a sensitive function of plasma parameters at the location where the source waves overlap. This fluctuation can be detected from outside the plasma, by measuring the deflection of a probe beam directed at the overlap region between the two pump waves (i.e., collective scattering). This work is an extension of mm-wave frequencies of a 10 GHz beat-wave experiment conducted on the DDT toroidal device (see Fig. 1) in a magnetized plasma where the excited Langmuir wave is replaced by the magnetized upper hybrid wave. Here, two high power (> 1 kW) ~94 GHz pump sources will be employed to match the upper hybrid resonance. The primary envisioned experiment is to drive the electron Bernstein wave (EBW) in the interior of a magnetized plasma. The EBW is a hot-plasma electrostatic wave, which cannot propagate in vacuum. Roots of the EBW dispersion relation occur at frequencies slightly higher than harmonics of the electron cyclotron frequency. Use of the EBW has particular advantages for measuring plasma magnetic field in plasmas with relatively high density and low magnetic field, as is the case in spherical tokamaks. This is the “over dense” condition of future efficient high beta magnetic confinement fusion reactors such as the spherical tokamak (STs). The overarching goal of the proposed project is to demonstrate beat wave EBW excitation in low density and temperature parameters that are directly scalable to over-dense spherical tokamaks such as NSTX or MAST, where measurement of magnetic field by electron cyclotron emission (ECE) is experimentally complex, and requires models of plasma profiles in order to interpret results. In such experiments, availability of point measurements of magnetic field strength provided by a beat-wave diagnostic would serve as a powerful independent check on the ECE results, serving to validate the assumed profiles and wave-propagation models used. The first step was to assemble/modify the target chamber in which the beat-wave plasma experiments will take place. Here, the target chamber of the CTIX compact-toroid (spheromak) injector was chosen. At the time that the proposal was submitted, the aim was to conduct the experiments in the CTIX experimental facilities located at the Livermore campus of UC Davis using microwave/mm-wave equipment brought from the main campus., However, by the time DoE funds for this project were awarded, the CTIX experimental facilities located at the Livermore campus of UC Davis were in the process of being shut down due to the closure of the Livermore campus by Lawrence Livermore National Laboratory (LLNL). Consequently, the equipment needed for this project was crated up and shipped from Livermore to Davis as part of the laboratory shutdown after space on campus was secured and College of Engineering approval secured. Once it arrived in Davis on December 20, 2018, work on the project began in earnest with the initial efforts directed toward developing a new plasma target source. Because of the shutdown of the CTIX facility, the scope of the project thus had to be reduced due to the abbreviated amount of time allocated to the project once the shutdown/move had been completed. Chamber modifications have been completed, including the fabrication and installation of a 38 GHz interferometer, as described in Sec. 3. The thermionic plasma source has been tested and characterized. The magnetic field required for the EBW experiments will be generated by permanent magnets mounted on plates positioned above and below the chamber. Magnetic simulations have been performed, and show that a 3-ring magnet arrangement on each plate, with a plate separation of 50 cm, is required to achieve the ~100 G uniform magnetic field in the interaction region that we feel is necessary to ensure good EBW coupling. We proved unable to successfully revive either of Prof. Luhmann’s two high power (≥20 kW) 94 GHz millimeter-wave sources after their extended time in storage and decided to postpone further efforts and concentrate on slightly lower power sources. Consequently, we were successful in reviving a ~2 kW extended klystron amplifier (EIK), which together with a ~2 kW extended interaction oscillator (EIO) will provide the two pump sources required for the project. Safe operation of the EIO requires extensive modifications to one of Prof. Luhmann’s pulse modulators - these modulator modifications are ongoing, which has unfortunately delayed the planned beat-wave experiments. Details of this work are provided in Sec. 3. Even though project funding has now ended, we still plan to proceed to complete the EIO pulse modulator modifications, install the two ~94 GHz pump wave sources on the target chamber, and conduct unmagnetized tests of the beat-wave concept which involve coupling to unmagnetized electron plasma waves rather than magnetized EBWs. Should these experiments prove successful, we plan to submit a follow-up proposal for additional funding which would allow us to undertake the magnetized EBW experiments.

42 ENGINEERING↗