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At least 1,315 records · Page 73

Feasibility of Using Additive Manufacturing to Produce Automotive Tooling

Oak Ridge National Laboratory’s (ORNL) Manufacturing Demonstration Facility (MDF) worked with Diversified Tooling Group (DTG) in phase I of this technical collaboration to determine the feasibility of using additive manufacturing to produce automotive tooling using polymer Big Area Additive Manufacturing (BAAM) systems and will potentially work with DTG in phase II on metal BAAM systems. The following phase I goals in polymer BAAM were met: a polymer sheet metal check fixture and a polymer foundry casting pattern were completed and shipped to DTG.

36 MATERIALS SCIENCE↗

Nevada National Security Site Waste Acceptance Criteria (NNSS/WAC)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); DOE classified waste/matter; U.S. Department of Defense (DOD) classified waste/matter The LLW and MLLW listed above may also be classified waste. Non-radioactive classified waste is accepted for disposal and shall meet the waste acceptance criteria for radioactive waste as specified in this document. Classified matter may be shipped to the NNSS for permanent burial as classified waste in accordance with the provisions in Section 3.1.18 of this document.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Summary of Observations from the 2017 Federal Radiological Monitoring and Assessment Center (FRMAC) Laboratory Analysis Training and Capstone Event

On August 15th thru 17th, 2017 the Federal Radiological Monitoring and Assessment Center (FRMAC) Laboratory Analysis division, the FRMAC Fly Away Laboratory (FAL), the FRMAC Assessment division, and the Mobile Environmental Response Laboratory (MERL) held a training and capstone event for staff from the Environmental Protection Agency (EPA), Remote Sensing Laboratory (RSL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratories (SNL). LAB-100, "Sample Control Training", LAB-200 "QA Specialist Training", and LAB-300 "Laboratory Analysis Manager Training" was given the first two days of the event. The purpose of the training and capstone event was to meet training requirements for billeted FRMAC Lab Analysis staff from RSL, LLNL, and SNL as well as raise awareness of the FRMAC Lab Analysis process with EPA staff as part of a Federal Emergency Management Agency — Nuclear Incident Response Team (FEMA-NIRT) laboratory standardization project. An objective of the standardization project was to help improve the transition of operations from DOE to EPA during a response. To do this effectively, detailed knowledge of the FRMAC Lab Analysis process by the EPA is needed. This training provided a good opportunity for this knowledge transfer. A capstone was held after the two-day training event to allow participants to practice the skills they learned in a realistic scenario. A scenario that was previously developed for a quarterly Consequence Management drill (i.e. Dark Phoenix) was used as the basis for the capstone, with laboratory analysis focused injects used to drive the exercise play. Each position within the FRMAC Lab Analysis Division exercised to specific objectives and helped to uncover gaps in the established processes. The lessons learned during this capstone are broken out in the following categories: Sample Control, In-Situ Gamma Spectroscopy, Analysis Request Forms (ARF), Shipping, QA/QC, Fly Away Laboratory (FAL), and Management.

54 ENVIRONMENTAL SCIENCES↗

Lessons from Past Nuclear Disarmament: What Worked What Did Not

This report studies the efforts of the international community and the United States to verif)/ the denuclearization of various countries: Ukraine, South Africa, Iraq, Taiwan, and Libya. In doing so, it considers the verification of nuclear warhead destruction and the accounting of nuclear materials. Each case study contributes to the understanding we have of which verification procedures worked and which did not and what factors contributed to that success and which did not. The most important factor contributing to successful verification is the cooperation of the subject country. If a country has made the strategic decision to cooperate, then it is possible that verification can be successful. If the country chooses not to cooperate, verification might rest on random and unpredictable events. This unpredictability of verification is politically unacceptable. Even if verification is judged to be successful by the implementing agencies, outsiders can cast doubts on it by pointing out small and potentially unavoidable errors in material amounts verified. It is vitally important to systematically preserve forensic evidence, especially shipping and receiving records to avoid just such issues. Historically, such records are the most important evidence in verifying denuclearization. Technology is far less important than forensic analysis of records. It does play a supporting role in verifying some declarations but there can be an enormous delay in drawing conclusions caused by the necessity to analyze statistically large samples of materials. The confidence one gets from such analysis can be delayed well past the time it is politically significant. The most important advance in technology would be to accelerate that sample analysis process.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Nb-on-Cu Cavities for 700-1500 MHZ SRF Accelerators

Single crystal films of Nb were grown on MGO; RRR≈570 was measured in ≈4 µm films of Nb; cross-section SEM images showed that macro-particles embedded in the film had the same (100) crystal structure as the bulk film and were well adhered, hence did not pose a problem for vortex penetration. We coated 1.3 GHz cavities inside our vacuum chamber. We showed that we could grow uniform films on such cavities, but the best Qo measured was ~2E8, not acceptable. Next we coated 1.3 GHz cavities when pumping directly on the cavity. Arguing that heaters inside the vacuum chamber might be contaminating the coating, we pumped directly on the cavity so that it could be heated from outside (in air). The best Qo measured was ≈1E9, a record for all our cavity deposition. However, this encouraging result was tempered by Q-slope, which we attributed to impurities in the film due to the dirty (non-clean room) environment at AASC. It was decided to install the CED apparatus at JLab, to assemble, clean and coat under cleaner conditions. We next coated 1.3 GHz cavity at JLab. After shipping and installing the CED apparatus at JLab, two coating runs were completed before the project ended. Due to arcs inside the vacuum (faulty current leads) the runs ended prematurely, with ≈0.7 µm films. Since we had learned from coupon work that film thickness >2 µm (preferably 4 µm) were essential for good RF performance, the negative results were understandable. Indeed, the quadrupole resonator coatings for Sarah Aull at CERN had also indicated that a 2 µm coating would show adequate RF quality for LHC upgrades and for the ILC. JLab now has acquired the apparatus and knowledge of its operation. It is hoped that JLab will continue this potentially rewarding development and soon show the results that have eluded us.

43 PARTICLE ACCELERATORS↗

Sister Rod Nondestructive Examination Final Report

This report documents work performed under the Spent Fuel and Waste Disposition for the US Department of Energy (DOE) Office of Nuclear Energy (NE) Spent Fuel and Waste Science and Technology program. This work was performed to fulfill the Level 2 Milestone M2SF-17OR010201021, “Documentation of Non-destructive Tests on Sister Pins,” within work package SF-17OR01020102. The High Burnup Spent Fuel Data Project, sponsored by DOE-NE, is focused on understanding the effects of long-term storage and transportation on high burnup (HBU) (>45 gigawatt days per metric ton uranium) light water reactor fuel. The goals of the project are to “provide confirmatory data for model validation and potential improvement, provide input to future spent nuclear fuel (SNF) dry storage cask design, support license renewals and new licenses for Independent Spent Fuel Storage Installations (ISFSIs), and support transportation licensing for high burnup SNF". In support of project goals, 25 sister rods were removed from fuel assemblies at the North Anna Power Station. Nine rods were removed from the project assemblies, and 16 rods were removed from similar HBU assemblies. The 25 sister rods were shipped to Oak Ridge National Laboratory (ORNL) Irradiated Fuels Examination Laboratory (IFEL) in early 2016 for detailed nondestructive examination (NDE) and destructive examination (DE). The detailed examinations will provide essential information on the physical state of the HBU rods and the fuel contained in the rods prior to loading, drying, and long-term dry storage. Similar tests will be performed at the end of the long-term storage period to identify any changes in the fuel rods’ properties during the dry storage period.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Determining Patterns from Radiation Portal Monitor Data: Enabling Data Insight with Visual and Interactive Exploratory Data Analysis

Smuggling of nuclear and radiological material is a complex problem that will need to be analyzed from a variety of angles in order to effectively combat something so rare, yet so hazardous. One crucial tool in the effort to detect and deter smuggling of rad/nuc materials is the radiation portal monitor (RPM)—machines that scan passengers at airports, vehicles and trains at border crossings, and shipping containers at ports throughout the world. While data from RPMs are regularly analyzed at the individual lane level to ensure monitor health and good operation, aggregate analysis of the data has not gone far beyond summary statistics such as number of occupancies and alarm rates. In particular, there are opportunities to carry out interactive exploratory data analysis with the help of tools like the R package Shiny and methods that lend themselves to the visual display of spatiotemporal correlations such as spatial PCA and detrended cross-correlation analysis. By doing so, we discover interesting spatiotemporal patterns in the data that point to specific events or anomalous moments in time that warrant further analysis.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Los Alamos National Laboratory Input for the National TRU Program 5 Year Plan for National Nuclear Security Administration TRU Waste

On July 16, 2018, Los Alamos National Security (LANS) received a Corporate Board Data Call for Los Alamos National Laboratory (LANL) site input to the National TRU Program 5 Year Plan from the Office of the National TRU Program. This report summarizes LANL input for the National Nuclear Security Administration (NNSA) TRU waste and captures the shipping needs to support the LANL mission. Information is included for the current waste inventory and projected generation rates. The site’s location, characteristics, role and mission are described. Additional information for consideration and pictures for inclusion are provided. A separate submittal will be prepared by N3B for LANL legacy TRU waste managed by N3B under contract to EM-LA.

, LANL↗

Payload Production for the Fire Testing of Primary Containment Vessels

One safety concern for the storage of nuclear or hazardous materials within the Department of Energy (DOE) complex is the pressure response behaviors of Primary Containment Vessels (PCVs) of a 9975 shipping package. Although there are many conservative estimates for the pressure response behavior of PCV in high temperature environments, these estimations remain unchecked by experiment. Conservative estimates frequently build in large safety margins which result in a reduced operating range and potentially unnecessary operation restrictions. In an attempt to alleviate some of these barriers, Nuclear & Criticality Safety Engineering (N&CSE) has requested the fire testing of primary containment vessels.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Model FL O-ring Thermal Testing Results

The objective of this test series was to determine the low and high failure temperatures of three different O-ring material compounds in the context of the Model FL shipping container main seal (inner o-ring).

42 ENGINEERING↗

Saltstone First Quarter Calendar Year 2018 (1QCY18) 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 first quarter of calendar year 2018 (1QCY18). Results from this memorandum support Task 2: ‘Grout Leaching Analyses’ of the Task Technical Request (TTR). 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 1QCY18 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 Saltstone WAC.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Saltstone First Quarter Calendar Year 2018 (1QCY18) 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) sample1 and Z-Area premix material for the first quarter of calendar year 2018 (1QCY18). 2,3 Results from this memorandum support Task 2: ‘Grout Leaching Analyses’ of the Task Technical Request (TTR). 2 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). 4 The 1QCY18 saltstone sample met the South Carolina (SC) Code of Regulations for Hazardous Waste Management Regulations (HWMR) 6 1-79.261.24 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 Saltstone WAC.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Accident Tolerant Fuels Series 1 (ATF-1) Irradiation Testing FY 2017 Status Report

This report contains a summary of irradiation testing of FCRD ATF-1 experiments performed at the INL in FY 2017. ATF-1 irradiation testing work performed in FY 2017 included fabrication of one ATF-1B drop in capsule ATF-1 series experiment and irradiation testing of ATF-1 capsules in the ATR. Additionally, five capsules met the sponsor-specified burnup targets, three of which were shipped from the ATR to the HFEF at INL.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Low-GWP HVAC System with Ultra-small Centrifugal Compression

Mechanical Solutions, Incorporated (MSI) was awarded a contract from the United States Department of Energy under Contract DE-EE0007042 to advance the potential of vapor compression utilizing an advanced high speed centrifugal compressor with an advanced heat exchanger design. The design was mandated to maintain high efficiency while utilizing a low GWP refrigerant. The specific goal of this program was to develop an advanced 5 ton air conditioning system. The target of the air conditioner is residential and commercial. To accomplish these goals, MSI teamed with Lennox International, a leading air conditioning manufacturer. MSI would design, oversee manufacturing, assemble, and test the compressor, while Lennox designed the heat exchanger and tested the overall air conditioner. Lennox initiated the project with a detailed cycle analysis that examined systems and refrigerants. At various break points, MSI performed a preliminary compressor design to identify realizable targets. Initially, the refrigerant that was targeted was R1234ze(E), but this was subsequently rejected over concerns of flammability. R515a was ultimately accepted as a qualified fluid based upon its GWP and flammability rating. MSI performed a complete design of the centrifugal compressor based upon the cycle system design and analysis. The design was based upon advanced aerodynamics utilizing transient Computational Fluid Dynamics (CFD), as well as mechanical and rotordynamic analysis. A detailed materials investigation was conducted to ensure mechanical integrity and refrigerant compatibility. To achieve the high rotational speed required by the compressor (105,300 rpm), foil bearings were designed by MSI, as was a high speed motor to provide the required torque for the compressor. All elements of the design complied with Design for Manufacturing and Assembly (DFMA) principles. The compressor was manufactured in components, utilizing specializing subcontractors throughout the country. The components were assembled into an operational compressor in MSI’s Albany facility, where it was tested in the MSI refrigeration test loop. The compressor achieved 90% of its maximum speed during testing at MSI. The interaction between the inverter and the high speed motor was the reason that full speed could not be attained. The compressor operated smoothly and quietly at all speeds, with the bearings performing as expected. The compressor was then shipped to Lennox’s facilities in Texas, where it was tested in the entire air conditioning system. Lennox was able to achieve 95% of the maximum rotational speed. They employed the same inverter as MSI. Lennox compiled the results of the testing and based upon the results, a go forward plan has been developed to correct the issues with the inverter, as well as redesign some parts that proved to be a challenge during the program. The consensus of the team is that a fully functional air conditioning system can be developed to achieve all of the goals identified in this program.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Biologically Inspired Ammonia Production with Immobilized Nitrogenase Final Report

Ammonia is a critical component of the US economy as US agricultural exports exceeded $100BB in 2015 and depend heavily on ammonia fertilizers. Ammonia production consumes 1% of the world’s total energy supply and millions of tons are imported each year. An innovative bioelectrocatalyzed process is being developed using immobilized mutated nitrogenase enzymes to directly convert atmospheric nitrogen to ammonia at standard conditions, 25° C and 1 atm, and without the need for natural gas. This technology utilizes an enhanced enzyme and advanced enzyme immobilization method for increased production efficiency. The Phase I project developed a new enzyme and polymer support structure which enables direct conversion of nitrogen to ammonia under mild conditions without the need for added chemicals; only electricity and water are required. The system exhibited significantly higher efficiency than competing technologies. The Phase II project will develop a commercial process for the enzyme/polymer system. This will include scaling up production of the enzyme and determining process conditions for maximum productivity. This technology is intended for the commercial fertilizer industry, which currently uses large, expensive plants for centralized production, consuming vast amounts of natural gas and generating significant CO 2 pollution. This technology could also be used to generate alternative ammonia-based fuel and ammonia-based commodity chemicals. The Federal Government would benefit from this technology by reducing dependence on foreign imports, and increasing domestic production of a commodity chemical. Ammonia is used as key component in explosives and propellants and is essential for national security. Distributed production will lower the vulnerability of this resource. The key benefit for the customer is lower capital and operating cost. Building new ammonia production plants cost >$2BB with considerable infrastructure costs to ship the ammonia. The primary method of transportation is pipe to truck distribution, although some is still carried via railway. The feature that set our technology apart from the current Haber-Bosch process is the ability for low-cost distributed production.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Special Purpose Application Reactors: Systems Integration Decision Support

Microreactors, also known as very-Small Modular Reactors (vSMRs) or Special Purpose Reactors (SPRs), are being considered for use in unique applications where other methods of megawatt level energy production are uneconomical or unavailable. For the purposes of this report, a microreactor is defined as meeting the following criteria: • Factory manufacturable • Easily transportable by truck, plane, train, and/or ship • Produce no more than 20 megawatt thermal (MWth) energy, in order to qualify as Hazard Category 2 under 10CFR830 • Maintains neutronic simplicity, allowing semi- or fully-autonomous operation In the United States (U.S.), there are two general types of microreactors under development: high-temperature gas reactors (HTGRs) and heat pipe reactors. These two reactor types may, due to their differences in working fluid temperatures, be more effectively suited to different use cases. Additionally, they will require different interfacing components depending on their intended use. This report identifies a broad range of use cases for micro-reactors. Additionally, multiple reactor technologies are examined with an emphasis on the reactor sub-systems and interconnections. Using this information, a decision framework is developed to guide future efforts.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Results of Hg Speciation Testing on the 2Q18 Tank 50 Sample

The Savannah River National Laboratory (SRNL) was tasked with preparing and shipping samples for Hg speciation by Eurofins Frontier Global Sciences, Inc. in Seattle, WA on behalf of the Savannah River Remediation (SRR) Mercury Task Team. The thirty-second shipment of samples contained the 2Q18 Tank 50 WAC.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Measurement of Average Burnup in TRISO-Coated Particles from AGR-2 UCO Compacts 2-2-2 and 6-4-2

Burnup analysis was performed on tristructural-isotropic (TRISO)-coated particles deconsolidated from compacts irradiated by the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program in the second irradiation experiment (AGR-2) [Collin 2014]. The AGR-2 irradiation experiment included TRISO fuel particles with kernels containing both uranium oxide and uranium carbide, called UCO, where uranium carbide is included with the commonly-used uranium oxide in the kernel to provide a getter for oxygen liberated during fission and limit CO production. This allows the UCO-TRISO particles to be taken to higher burnup without failure from excessive internal CO pressure or CO-corrosion of the SiC layer. The UCO kernels were fabricated and coated at BWX Technologies Nuclear Operations Group (BWXT-NOG) with a 150-mm-diameter engineering-scale coater. The UCO-TRISO batch used in the AGR-2 irradiation experiment was Batch 93073, which had kernels with an average diameter of 426.7 μm and average coating thicknesses moving out from the kernel of 98.9 μm (buffer), 40.4 μm (IPyC), 35.2 μm (SiC), 43.4 μm (OPyC) [Barnes and Marshall 2009]. The TRISO particle were shipped to ORNL to be formed into compacts for irradiation testing. The compact lot qualified for the AGR-2 irradiation test was lot LEU09-OP2-Z and had an average of 3176 UCO-TRISO particles in each compact [Hunn, Montgomery, and Pappano 2010]. Compilations of the properties data for the particles and compacts are available in a pre-irradiation characterization summary report for the AGR-2 fuel composites [Hunn, Savage, and Silva 2010].

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗