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PRP Comments for ICF Q1/Q2 FY17 Experiments 3/10/16

The PRP generally endorsed the Program plan during the short time for discussions. We agree that the strategy to develop a hohlraum that is symmetric and has low laser-plasma instabilities and to develop an alternative method for supporting the capsule is the best path forward for making progress in understanding ignition performance. The Program is oriented toward a milestone in 2020 for “determining the efficacy of NIF for ignition and credible physics-scaling to multi-megajoule yields for all ICF approaches.” We are concerned that the time and resources are not sufficient to vet all of the various approaches that are being pursued to make an informed decision by this date. For NIF to meet this goal, a process will be needed to to select the most promising paths forward. We recommend that the Program develop this process for selecting the path forward to optimize resources. We were glad to see that the direct drive program took our comments under consideration. We think that the proposed experiments have the program headed in a better direction. The PRP had only a short time to discuss the detailed experimental proposals. The following are comments on the detailed proposals. We did not have time to discuss them as a group. They represent individual opinions and provided to you as feedback to your proposals.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Comprehensive Review of DPF-based Flash Neutron Radiography Viability

MJOLNIR (MegaJOule Neutron Imaging Radiography) is a Dense Plasma Focus (DPF) being developed by LLNL as a prototype to assess the viability of a DPF as a flash neutron radiography source. To date, MJOLNIR has discharged up to 1.3 MJ of stored energy into a deuterium plasma load and achieved yields up to 1.2 × 10 12 neutrons per discharge. The MJOLNIR pulse length already meets the preliminary requirements for flash neutron radiography and we demonstrate in this report plausible paths forward to meet the yield requirement in a deuterium plasma. MJOLNIR’s neutron spot size has been characterized to be a factor of two greater than radiography requirements and presents the greatest challenge. A path forward to sufficiently shrinking spot size is outlined in this report, using a combination of gas dopants and a smaller anode implosion radius. A DPF is a plasma device with coaxial electrodes whose discharge ends with a stagnated hot and dense plasma column on-axis, at the tip of the central anode. Inside the MJOLNIR DPF plasma column, both thermal and beam target processes generate neutrons. To understand the underlying physics of neutron generation inside the DPF, we model the experiment using a combination of kinetic, fluid, and reduced-order models we have been developing for over ten years at LLNL. Our numerical tools are also pivotal to charting the path forward because they allow us to numerically test out which modifications would improve the DPF’s characteristic output.

42 ENGINEERING↗

Panel Session 76: US DOE Problematic Waste Streams and Policy Impacts

This panel provided an overview of DOE problematic waste streams including status and path forward. Potential policy implications that exist now and/or in the future were discussed. Topics included, greater-than-Class C low level waste, depleted uranium, and sodium waste. The panel also discussed potential treatment options for these wastes. As part of the introduction, Renee Echols welcomed the audience and went over a quick overview of what would be discussed on the panel. Theresa Kliczewski provided an overview of why this panel is relevant to US Department of Energy's Office of Environmental Management: there are problematic waste streams that still exist across the DOE cleanup complex. Theresa noted that the DOE EM Headquarters Office of Waste and Materials Management (EM-4.2), for which she is employed with, continues to work with the DOE cleanup sites on a path forward for these problematic waste streams. Presentations proposed include: 1 - Overview of Greater-Than-Class C Low-Level Radioactive Waste Disposal Path Forward (Theresa Kliczewski, US DOE EM (USA)); 2 - Status of Draft Supplemental Environmental Impact Statement for Disposition of Depleted Uranium Oxide Conversion Product Generated from DoE's Inventory of Depleted Uranium Hexafluoride (Jaffet Ferrer-Torres, US DOE (USA)); 3 - Problematic Waste Streams on the Oak Ridge Reservation (John Wrapp, UCOR (USA)); 4 - K Basin Sludge Removal (Ryan Covert, CH2M Hill PRC (USA)); 5 - Providing Technology Solutions for Treatment of Challenging Waste Streams (Tammy Monday, Perma-Fix Environmental Services (USA)); 6 - Treatment of Problematic Reactive Metal Waste Using the GeoMelt{sup R} In-Container Vitrification (ICV{sup TM}) Process (Ron Mitchell, Veolia Nuclear Solutions (USA))

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Analysis techniques for background rejection at the MAJORANA DEMONSTRATOR

The MAJORANA Collaboration is constructing the MAJORANA DEMONSTRATOR, an ultra-low background, 40- kg modular HPGe detector array to search for neutrinoless double beta decay in {sup 76}Ge. In view of the next generation of tonne-scale Ge-based 0νβ β-decay searches that will probe the neutrino mass scale in the inverted-hierarchy region, a major goal of the MAJORANA DEMONSTRATOR is to demonstrate a path forward to achieving a background rate at or below 1 count/tonne/year in the 4 keV region of interest around the Q-value at 2039 keV. The background rejection techniques to be applied to the data include cuts based on data reduction, pulse shape analysis, event coincidences, and time correlations. The Point Contact design of the DEMONSTRATOR’s germanium detectors allows for significant reduction of gamma background.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Status of the Majorana Demonstrator

The MAJORANA Collaboration is constructing the MAJORANA DEMONSTRATOR, an ultra-low background, modular, HPGe detector array with a mass of 44-kg (29 kg {sup 76}Ge and 15 kg {sup nat}Ge) to search for neutrinoless double beta decay in {sup 76}Ge. The next generation of tonne-scale Ge-based neutrinoless double beta decay searches will probe the neutrino mass scale in the inverted-hierarchy region. The MAJORANA DEMONSTRATOR is envisioned to demonstrate a path forward to achieve a background rate at or below 1 count/tonne/year in the 4 keV region of interest around the Q-value of 2039 keV. The MAJORANA DEMONSTRATOR follows a modular implementation to be easily scalable to the next generation experiment. First, the prototype module was assembled; it has been continuously taking data from July 2014 to June 2015. Second, Module 1 with more than half of the total enriched detectors and some natural detectors has been assembled and it is being commissioned. Finally, the assembly of Module 2, which will complete MAJORANA DEMONSTRATOR, is already in progress.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

The Majorana low-noise low-background front-end electronics

The Majorana Demonstrator will search for the neutrinoless double beta decay (ββ(0ν)) of the isotope ⁷⁶Ge with a mixed array of enriched and natural germanium detectors. In view of the next generation of tonne-scale germanium-based ββ(0ν)-decay searches, a major goal of the Majorana Demonstrator is to demonstrate a path forward to achieving a background rate at or below 1 cnt/(ROI-t-y) in the 4 keV region of interest (ROI) around the 2039-keV Q-value of the ⁷⁶Ge ββ(0ν)-decay. Such a requirement on the background level significantly constrains the design of the readout electronics, which is further driven by noise and energy resolution performances. We present here the low-noise low-background front-end electronics developed for the low-capacitance p-type point contact (P-PC) germanium detectors of the Majorana Demonstrator. This resistive-feedback front-end, specifically designed to have low mass, is fabricated on a radioassayed fused-silica substrate where the feedback resistor consists of a sputtered thin film of high purity amorphous germanium and the feedback capacitor is based on the capacitance between gold conductive traces.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Integration of the Back End of the Nuclear Fuel Cycle

Management of spent nuclear fuel and high-level radioactive waste consists of three main phases – storage, transportation, and disposal – commonly referred to as the back end of the nuclear fuel cycle. Current practice for commercial spent nuclear fuel management in the United States (US) includes temporary storage of spent fuel in both pools and dry storage systems at operating or shutdown nuclear power plants. Storage pools are filling to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler spent fuel from pools into dry storage. Unless a repository becomes available that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 136,000 metric tons of spent fuel in dry storage systems by mid-century, when the last plants in the current reactor fleet are decommissioned. Current designs for dry storage systems rely on large multi-assembly canisters, the most common of which are so-called “dual-purpose canisters” (DPCs). DPCs are certified for both storage and transportation, but are not designed or licensed for permanent disposal. The large capacity (greater number of spent fuel assemblies) of these canisters can lead to higher canister temperatures, which can delay transportation and/or complicate disposal. This current management practice, in which the utilities continue loading an ever-increasing inventory of larger DPCs, does not emphasize integration among storage, transportation, and disposal. This lack of integration does not cause safety issues, but it does lead to a suboptimal system that increases costs, complicates storage and transportation operations, and limits options for permanent disposal. This paper describes strategies for improving integration of management practices in the US across the entire back end of the nuclear fuel cycle. The complex interactions between storage, transportation, and disposal make a single optimal solution unlikely. However, efforts to integrate various phases of nuclear waste management can have the greatest impact if they begin promptly and continue to evolve throughout the remaining life of the current fuel cycle. A key factor that influences the path forward for integration of nuclear waste management practices is the identification of the timing and location for a repository. The most cost-effective path forward would be to open a repository by mid-century with the capability to directly dispose of DPCs without repackaging the spent fuel into disposalready canisters. Options that involve repackaging of spent fuel from DPCs into disposalready canisters or that delay the repository opening significantly beyond mid-century could add 10s of billions of dollars to the total system life cycle cost.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Additive Manufacturing of MITL's and Convolutes

Stockpile stewardship requires accurate and predictive models relying on the generation of extreme environments which is both incredibly difficult and profoundly necessary. Next generation pulsed power facilities (NGPPF), where these environments are created, may require a paradigm shift in equipment engineering/manufacture to fulfill this need. Therefore, this research aims to investigate the limitations, capabilities and efficacy of leveraging advancements in the field of additive manufacturing (AM) in order to produce novel power flow components for NGPPFs. This work focused on commercial 3D metal AM equipment producing several prototypes addressing prescient needs/shortcomings, and a technique wherein a lightweight polymer core is metalized. Ultimately, commercial 3D metal AM is considered a viable path forward but would require a sizeable investment and does not currently support the scale and complexity necessary for NGPPFs. Moreover, initial results from our composite technique are promising and is considered a realizable path forward given further investigation.

42 ENGINEERING↗

ROCM+Intel-PathForward+RemoteSpaces Development

This report documents the completion of milestone STPRO4-25 Harden and optimize the ROCm based AMD GPU backend, develop a prototype backend for the Intel ECP Path Forward architecture, and improve the existing prototype Remote Memory Space capabilities. The ROCM code was hardened up to the point of passing all Kokkos unit tests - then AMD deprecated the programming model, forcing us to start over in FY20 with HIP. The Intel ECP Path Forward architecture prototype was developed with some initial capabilities on simulators - but plans changed, so that work will not continue. Instead SYCL will be developed as a backend for Aurora. Remote Spaces was improved. Development is ongoing part of a collaboration with NVIDIA.

97 MATHEMATICS AND COMPUTING↗

LiCaAIF 6 :Eu Scintillator Family Neutron Detection (Final Report)

The proposed work was based on a learning cycle format with three parts, (1) Modeling, (2) Growth, (3) Characterization, to investigate the family of colquiriite scintillators and various activating dopants as efficiently and effectively as possible. Under this research methodology, each of these functions would feed information to the next. Each iteration around the cycle was expected to improve results and provide clues to the best path forward for the next iteration. However, it was realized that this research model is not robust and unable to handle setbacks at any one of the functions. Unfortunately, the project suffered setbacks in the “Growth” function and progress in the other functions was severely restricted. Of course, numerous alternative paths were trialed within the growth function to enable progress, but these required addition time and resources which in the end only provided limited progress. After reviewing the project as a whole, it can be concluded that the research model used was indeed too fragile for this sort of research and a more robust plan should be utilized in the future. As a whole though, significant progress was made toward understanding the barriers toward realizing the benefits of this family of scintillators through modeling. Various paths forward were postulated, but limited growth and synthesis capabilities prevented experimental validation. Experimentally, it was found that the synthesis and growth of colquiriite scintillators requires special considerations for its thermodynamic and chemical properties. These were overcome in the end and a new, lower cost growth method realized, but too late to have a significant impact in validating modeling hypotheses.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Summary Report of the Reactive CO 2 Capture: Process Integration for the New Carbon Economy Workshop

Decarbonization of our global economy is required to limit planetary warming to +1.5⁰C above pre-industrial levels, an ambitious goal set into motion by the Paris agreement. Given the scale and urgency, the solution demands international, cross-sector advancements spanning policy, social responsibility, and technology, with emphasis on step changes over incremental changes. To that end, technological revolutions that disrupt the status quo need to be envisioned and enacted. One potential technological revolution is the production of fuels, chemicals, and materials from carbon dioxide (CO 2 ) as the starting feedstock, leveraging renewable energy as the driving force. Over the past decades, significant research, development, and deployment has occurred on technologies for capturing CO 2 from point sources or the air and utilizing this CO 2 as a working fluid or as a chemical reactant; however, most of this work has been siloed in these two categories. Recently, an emerging field has started to explore the direct integration of CO 2 capture and conversion technologies as a means to reduce overall energy demand (i.e., avoid energy penalty of CO 2 desorption/regeneration of capture media) and capital expense through process intensification. This strategy represents an opportunity to leapfrog forward this technological revolution. However, the field is in its infancy and the technologies are at an early stage of development, thus it is critically important to define and assess the value proposition of this strategy relative to alternatives (e.g., separated capture and conversion technologies, fuels and chemicals derived from renewable feedstocks like biomass, and industrial electrification) to chart a path forward. To identify next steps, we organized a workshop titled “Reactive CO 2 Capture: Process Integration for the New Carbon Economy” which was held in Golden, Colorado, February 18–19, 2020. The focus of this workshop was to discuss approaches for merging CO 2 capture and CO 2 conversion/utilization systems into what we denoted as an integrated "reactive capture" strategy. By our definition, reactive capture of CO 2 is the coupled process of capturing CO 2 from a mixed gas stream and converting it into a valuable product without going through a purified CO 2 intermediate (see full definition in the Introduction section). This report seeks to summarize feedback from the approximately 125 participants and subject matter experts in attendance from academia, industry, U.S. Department of Energy (DOE), and DOE national laboratories. The workshop agenda is included in Appendix A and the full list of attendees can be found in Appendix B. To elucidate a path forward, we first asked the attendees to define what success would look like for reactive capture in the short term (0–5 years), midterm (5–10 years), and long term (10+ years) and then asked them to answer four questions related to how we could achieve that success: (1) What are the key barriers and challenges to success? (2) What are needed activities to overcome barriers and challenges? (3) What opportunities will arise from these activities? (4) What is a target outcome and what metrics need to be met?

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

MO-DE-304-00: Workforce Assessment Committee Update

The Abt study of medical physicist work values for radiation oncology physics services, Round IV is completed. It supersedes the Abt III study of 2008. The 2015 Abt study measured qualified medical physicist (QMP) work associated with routine radiation oncology procedures as well as some special procedures. As before, a work model was created to allow the medical physicist to defend QMP work based on both routine and special procedures service mix. The work model can be used to develop a cost justification report for setting charges for radiation oncology physics services. The Abt study Round IV was designed to empower the medical physicist to negotiate a service or employment contract with providers based on measured national QMP workforce and staffing data. For a variety of reasons, the diagnostic imaging contingent of AAPM has had a more difficult time trying estimate workforce requirements than their therapy counterparts. Over the past several years, the Diagnostic Work and Workforce Study Subcommittee (DWWSS) has collected survey data from AAPM members, but the data have been very difficult to interpret. The DWWSS has reached out to include more AAPM volunteers to create a more full and accurate representation of actual clinical practice models on the subcommittee. Though much work remains, through hours of discussion and brainstorming, the DWWSS has somewhat of a clear path forward. This talk will provide attendees with an update on the efforts of the subcommittee. Learning Objectives: Understand the new information documented in the Abt studies. Understand how to use the Abt studies to justify medical physicist staffing. Learn relevant historical information on imaging physicist workforce. Understand the process of the DWWSS in 2014. Understand the intended path forward for the DWWSS.

60 APPLIED LIFE SCIENCES↗

MO-DE-304-01: The Abt Study of Medical Physicist Work Values for Radiation Oncology Physics Services: Round IV

The Abt study of medical physicist work values for radiation oncology physics services, Round IV is completed. It supersedes the Abt III study of 2008. The 2015 Abt study measured qualified medical physicist (QMP) work associated with routine radiation oncology procedures as well as some special procedures. As before, a work model was created to allow the medical physicist to defend QMP work based on both routine and special procedures service mix. The work model can be used to develop a cost justification report for setting charges for radiation oncology physics services. The Abt study Round IV was designed to empower the medical physicist to negotiate a service or employment contract with providers based on measured national QMP workforce and staffing data. For a variety of reasons, the diagnostic imaging contingent of AAPM has had a more difficult time trying estimate workforce requirements than their therapy counterparts. Over the past several years, the Diagnostic Work and Workforce Study Subcommittee (DWWSS) has collected survey data from AAPM members, but the data have been very difficult to interpret. The DWWSS has reached out to include more AAPM volunteers to create a more full and accurate representation of actual clinical practice models on the subcommittee. Though much work remains, through hours of discussion and brainstorming, the DWWSS has somewhat of a clear path forward. This talk will provide attendees with an update on the efforts of the subcommittee. Learning Objectives: Understand the new information documented in the Abt studies. Understand how to use the Abt studies to justify medical physicist staffing. Learn relevant historical information on imaging physicist workforce. Understand the process of the DWWSS in 2014. Understand the intended path forward for the DWWSS.

60 APPLIED LIFE SCIENCES↗

MO-DE-304-02: Diagnostic Workforce Subcommittee Status and Direction

The Abt study of medical physicist work values for radiation oncology physics services, Round IV is completed. It supersedes the Abt III study of 2008. The 2015 Abt study measured qualified medical physicist (QMP) work associated with routine radiation oncology procedures as well as some special procedures. As before, a work model was created to allow the medical physicist to defend QMP work based on both routine and special procedures service mix. The work model can be used to develop a cost justification report for setting charges for radiation oncology physics services. The Abt study Round IV was designed to empower the medical physicist to negotiate a service or employment contract with providers based on measured national QMP workforce and staffing data. For a variety of reasons, the diagnostic imaging contingent of AAPM has had a more difficult time trying estimate workforce requirements than their therapy counterparts. Over the past several years, the Diagnostic Work and Workforce Study Subcommittee (DWWSS) has collected survey data from AAPM members, but the data have been very difficult to interpret. The DWWSS has reached out to include more AAPM volunteers to create a more full and accurate representation of actual clinical practice models on the subcommittee. Though much work remains, through hours of discussion and brainstorming, the DWWSS has somewhat of a clear path forward. This talk will provide attendees with an update on the efforts of the subcommittee. Learning Objectives: Understand the new information documented in the Abt studies. Understand how to use the Abt studies to justify medical physicist staffing. Learn relevant historical information on imaging physicist workforce. Understand the process of the DWWSS in 2014. Understand the intended path forward for the DWWSS.

60 APPLIED LIFE SCIENCES↗

Mercury Speciation via Direct Mercury Analyzer

Mercury has no known biological role, but is present in every living thing and widespread in the environment. As mercury enters an aqueous system, it is subject to methylation or demethylation. Methylmercury selectively partitions into biota and biomagnifies through the food chain. Nearly all methylmercury exposures in the U.S. occur through eating fish and shellfish that contain higher levels of methylmercury. Methyl mercury and other organomercury compounds are more toxic than inorganic mercury. Thus, monitoring and understanding mercury speciation are key to effective environmental management. It is particularly important to be able to separate and measure bioaccumulative-toxic species of mercury such as methyl mercury. We are developing a protocol for utilizing the Direct Mercury Analyzer (DMA-80) for mercury speciation of water samples and to monitor methylmercury (meHg). Objectives: - Advance the understanding of the performance of the direct mercury analysis (DMA) under a range of DOE relevant water chemistry conditions to quantify total mercury: - Demonstrate the applicability of DMA to analysis of typical DOE high level liquid 'tank' waste samples using nonradioactive simulants; Test innovative sorbents to extend the range of the direct mercury analyzer to environmental concentration levels. - Perform scoping tests to demonstrate proof of principle for the chemical reduction amalgamation modular microcolumns for mercury speciation: Examine various microcolumn configurations and document speciation performance for typical DOE high level liquid 'tank' waste samples using nonradioactive simulants; Perform tests to examine extending the speciation paradigm to environmental concentration levels. General Method: all samples analyzed using a direct mercury analyzer (DMA 80) which automates the following steps: 1) pyrolysis to release the mercury, 2) catalysis to convert all mercury to elemental, 3) amalgamation to trap the mercury, 4) desorption to release the mercury as a pulse and 5) spectroscopy to detect the mercury.. Instrument analyzes all mercury species in solids and liquids. The DMA 'eliminates' sample preparation, reduces labor, decreases waste, and results in more practical and cost effective methods. To test the performance of the DMA for DOE relevant conditions, we analyzed samples representative of at high (mg/L) tank waste concentrations in water and in diluted tank waste simulant and analyzed samples representative of environmental (ng/L levels) in water. High concentration samples were analyzed directly in the instrument. Low concentration samples were analyzed by concentrating the mercury onto sorbents such as silica thiol or a mixture of silica thiol and copper. The concentration was performed using microcolumns and placing the columns into the DMA (see below) or by mixing the sorbent into the bulk sample and then filtering ad analyzing the filter in the DMA. Speciation Methods: The speciation tests were based on the selective reduction of inorganic mercury ions - Hg{sup (+} {sup or} {sup 2+)} - to elemental mercury - Hg(0). The elemental mercury is then trapped by amalgamation into the metal. These reactions do not impact methyl mercury allowing for separation. All reactions were performed using powdered elemental copper. To demonstrate proof-of-principle for the selective collection of inorganic mercury, samples were exposed to different amounts of powdered copper (and a control with no copper). This was done using microcolumns and a vacuum box. The columns were placed directly on the DMA for analysis. All materials and conditions were tested using solutions of both inorganic mercury and methyl mercury and all trials were in triplicate. Results and Observations: Validated DMA for high concentration Hg samples such as DOE tank waste: - Liquid inHg - samples were stable on autosampler carousel and results were accurate; - Liquid meHg - samples required a stabilizer. Si-Thiol (0.02 g) in the sample boat generated reliable meHg results. Stabilizer can be added for routine operations. Successful 'proof of principal' in extending DMA range to near environmental levels - using both microcolumns and filtration; - Filtration - Adding Si-Thiol (0.5 g) to sample extracted both inHg and meHg and preserved sample. Handling filters was labor intensive. - Microcolumns - best performance using a combination of copper and Si-Thiol - columns clogged and flowed slowly in some cases; - Practical limit may be in the range of 1 to 5 ng/L due to blanks; - Path Forward - Test additional packing materials and methods to improve flow and consistency, and approaches to minimize blanks. Successful 'proof of principal' for Hg speciation using chemical reduction and amalgamation; - Copper microcolumns (0.5 g Cu) selectively trapped inHg for high concentration mercury samples; - Copper microcolumns (0.5 g Cu selectively trapped inHg for large volume samples at environmental concentrations; - Some sorption of me Hg so that separations not quantitative; - Path Forward - test additional packing materials and alternate eluents to better trap inHg and minimize meHg retention in column.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Sparingly solvating electrolytes for high energy density Lithium–sulfur batteries

Moving to lighter and less expensive battery chemistries compared to lithium-ion requires the control of energy storage mechanisms based on chemical transformations rather than intercalation. Lithium sulfur (Li/S) has tremendous theoretical specific energy, but contemporary approaches to control this solution-mediated, precipitation-dissolution chemistry requires using large excesses of electrolyte to fully solubilize the polysulfide intermediate. Achieving reversible electrochemistry under lean electrolyte operation is the only path for Li/S to move beyond niche applications to potentially transformational performance. An emerging topic for Li/S research is the use of sparingly solvating electrolytes and the creation of design rules for discovering new electrolyte systems that fundamentally decouple electrolyte volume from reaction mechanism. Furthermore, this perspective presents an outlook for sparingly solvating electrolytes as the key path forward for longer-lived, high-energy density Li/S batteries including an overview of this promising new concept and some strategies for accomplishing it.

25 ENERGY STORAGE↗

Status of the Majorana Demonstrator

The Majorana Collaboration is constructing the Majorana Demonstrator, an ultra-low background, 40-kg modular high purity Ge detector array to search for neutrinoless double-beta decay in 76 Ge. In view of the next generation of tonne-scale Ge-based neutrinoless double-beta decay searches that will probe the neutrino mass scale in the inverted-hierarchy region, a major goal of the Demonstrator is to demonstrate a path forward to achieving a background rate at or below 1 count/tonne/year in the 4 keV region of interest around the Q-value at 2039 keV. Lastly, the current status of the Demonstrator is discussed, as are plans for its completion.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Component Testing Supporting SHINE Medical Technologies

SHINE is going to be implementing a tritium gas processing system to support their Mo-99 work. They have requested that the Hydrogen Process Group of SRNL does some required testing on the system components before startup. The lab plans on conducting both seismic and valve testing. Test Plan: - Testing 10 1C valves 750,000 cycles or until failure; - Testing intervals will be every couple thousand; - 1C valves will have metal stem tips instead of Polymer due to being in a tritium prone area; - Hope that the valves will still have enough force to create a sufficient seal with metal stem tips; - Goal is for a more cost and space efficient alternative to the 5C valves. Status: - Received half the parts, waiting on the other half due to long procurement times; - Waiting on the LabVIEW program which will perform the testing. Path Forward: - R and DE to change out the stem tips (July 2018); - Assemble Manifold (July 2018); - Perform Testing (August 2018); - Report (September 2018). Since SRNL does not own a shaker table, the test will be conducted at a facility like the NTS Facility in Huntsville, Alabama. Test Plans: - Leak Testing; - Use LabVIEW to monitor for leaks before, during and after seismic testing with an Electronic Pressure Transducer; - If leak is detected, sniff for location using Helium Leak Detector; - Connector Testing; - Use LabVIEW to test for electrical continuity before, during and after seismic testing; - If a connectors continuity is interrupted, further testing will be performed; - Each Pin in faulty connector will be testing to determine specific location of disruption. Path Forward: - Pick a Qualified Vender for testing (July 2018); - Procure the connector plugs (July 2018); - Send components and test plan to facility for testing (August 2018); - Perform Testing (August-September 2018); - Report Results (September 2018)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗