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At least 739 records · Page 41

Electrochemical Solution Growth of Bulk GaN for Power Electronics Substrates, Final Report

This project focused on developing a novel, scalable, and economic growth technique for bulk gallium nitride (GaN), a critical material for next-generation high-temperature power electronics. Large area, high-quality bulk GaN is required as a substrate material in order to grow highly efficient bipolar transistors for inverters and power conditioning. Attempting to grow GaN in bulk by traditional precipitation methods forces extreme thermodynamic and kinetic conditions, putting these techniques at the extremes of experimental science, which is unsuitable for large-area, cost-effective substrate growth. The Electrochemical Solution Growth (ESG) technique is a novel concept that addresses these issues in a unique way, and was developed at Sandia National Laboratories (SNL), in part under this program. The crucial step in demonstrating the technique’s feasibility was to deposit high-quality GaN on a seed crystal. The bulk of SNL’s activities were focused on developing conditions for deposition of GaN on a seed crystal (a thin film of GaN grown by metal organic chemical vapor phase deposition (MOCVD) on c-axis oriented sapphire) in a molten salt electrolyte solution using a rotating disk reactor (RDR) ESG apparatus. This project was actively funded from FY08 to FY12 by the Energy Storage Program and GaN Initiative for Grid Applications (GIGA) program of the Office of Electricity Delivery and Energy Reliability (OE) in the U.S. Department of Energy (DOE). Some activities focused on silicon doping of GaN occurred in FY13 but only through the use of carryover funds.

36 MATERIALS SCIENCE↗

Evaluation of High Temperature Elastomers for Geothermal Wells

This report describes the extension of a performance screening study of elastomers for geothermal well applications. Elastomeric O-rings were subjected to compression while submerged in water at elevated temperatures and pressure to determine performance under more aggressive conditions. Following the experiment, the elastic moduli of the O-ring cross-sections were assessed for any changes which may affect O-ring function down-hole. All materials showed susceptibility to thermo-oxidative degradation at high temperatures and pressures. Type I FKM had the least amount of compression set of all materials tested at 150ºC while Kalrez FFKM O-rings had the least amount of edge hardening of all materials, regardless of aging temperature. Prior visual observation of materials aged in simulated environments revealed an unusual trend with EPDM and FEPM materials: the degradation and disintegration of these polymers in an oxidative thermal cycle environment, but the ability to maintain mechanical performance and shape during oxidative thermal cycling in the presence of steam. EPDM and FEPM were subjected to additional testing at SNL in order to better understand this aging anomaly. No abnormalities were observed in the chemical (oxidation rates, FTIR spectra, solvent uptake, gel content, and weight loss vs. temperature) or physical (modulus profiles) measurements that could explain the visually observed aging differences. SNL validated this observation through a secondary controlled aging test using only EPDM, where, once again, it was shown that thermo-oxidative conditions appear to cause more degradative damage (enhanced embrittlement) than did thermo-oxidative coupled with hydrolytic environments. From these data we conclude that water may favorably interfere with normal thermo-oxidative degradation processes via some type of inhibition pathway which has yet to be identified.

15 GEOTHERMAL ENERGY↗

Special Analysis for the Disposal of Sandia National Laboratory Line Generated Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis report evaluates whether the Sandia National Laboratory (SNL) Line Generated Waste is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the SNL Line Generated waste meets all DOE M 435.1-1 performance objectives.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

1997 Sanitary Sewer Master Plan

The sanitary sewer system at Lawrence Livermore National Laboratory (LLNL) is designed to collect and transport wastewater from LLNL and Sandia National Laboratories (SNL). The system was installed in stages, beginning in 1942, and underwent a massive rehabilitation between 1993 and 1995. The existing system is a shallow small pipe collection system of 96,300 linear feet that consists of mainlines, building laterals, manholes, waste retention facilities, a diversion facility and a monitoring station. On average, each day nearly 300,000 gallons of wastewater from LLNL and SNL enters the City of Livermore collection system from an outfall at LLNL's northwest corner.

42 ENGINEERING↗

Updated Stormwater Management Program Plan: For coverage under the National Pollutant Discharge Elimination System Municipal Separate Storm Sewer System Permit for stormwater discharges within the Middle Rio Grande Watershed (v.3)

The SWMPP describes the best management practices (BMPs) employed at SNL, measurable goals, and anticipated implementation dates for compliance with the Permit requirements to ensure that stormwater discharges from the SNL MS4 do not contribute pollutants to Waters of the United States (WOTUS), namely the Tijeras Arroyo and the Rio Grande. The SWMPP is updated annually, and as necessary, to include new information and/or document the development, implementation and assessment of program elements, as required in Part III.B of the Permit. Version 3 of the SWMPP documents compliance activities and program elements developed and implemented between July 1, 2016 and June 30, 2017; it is required to be submitted on or before December 1, 2017.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Pipe Overpack Container Fire Testing: Phase II-A

The Pipe Overpack Container (POC) was developed at Rocky Flats to transport plutonium residues with higher levels of plutonium than standard transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In 1996 Sandia National Laboratories (SNL) conducted a series of tests to determine the degree of protection POCs provided during storage accident events. One of these tests exposed four of the POCs to a 30-minute engulfing pool fire, resulting in one of the 7A drum overpacks generating sufficient internal pressure to pop off its lid and expose the top of the pipe container (PC) to the fire environment. The initial contents of the POCs were inert materials, which would not generate large internal pressure within the PC if heated. However, POCs are now being used to store combustible Transuranic (TRU) waste at Department of Energy (DOE) sites. At the request of DOE's Office of Environmental Management (EM) and National Nuclear Security Administration (NNSA), SNL started conducting a new series of fire tests in 2015 to examine whether PCs with combustibles would reach a temperature that would result in (1) decomposition of inner contents and (2) subsequent generation of sufficient gas to cause the PC to overpressurize and release its inner content. In 2016, Phase II tests showed that POCs tested in a pool fire failed within 3 minutes of ignition with the POC lid ejecting. These POC lids were fitted with an all-metal (NUCFIL019DS) filter and revealed that this specific filter did not relieve sufficient pressure to prevent lid ejection. For the test phase discussed in this report, Phase II-A, the POCs are exposed to a 30-minute pool fire, with similar configurations to those tested in Phase II, except that the POC lids are fitted with a hybrid metal-polyethylene (UT9424S) filter instead. This report will: describe the various tests conducted in Phase II-A, present results from these tests, and discuss implications for the POCs based on the test results.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Unreviewed Disposal Question Evaluation: Disposal of the Sandia National Laboratories Line Generated Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation assesses whether the Sandia National Laboratories (SNL) Line Generated Waste is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the waste stream meets all performance objectives in DOE M 435.1-1, Radioactive Waste Management Manual, Chapter IV, Section P. The SNL Line Generated Waste is recommended for acceptance with the following conditions: 1. Total 3H activity shall not exceed 5E14 Bq., 2. Total 226Ra activity shall not exceed 3E7 Bq., 3. Total 230Th activity shall not exceed 6E7 Bq., and 4. Total 234U activity shall not exceed 6E9 Bq.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Energy Harvesting RMSA Field Test

Sandia National Laboratories (SNL) is investigating photovoltaic (PV) cell configurations, integrating them with the battery-operated Remotely Monitored Sealing Array (RMSA), and testing and evaluating performance for enhanced battery life under various environmental conditions at the K-Area Material Storage (KAMS) facility at the Savannah River Site (SRS). Unattended safeguards equipment (e.g. seals) incorporates many low-power electronic circuits, which are often powered by expensive and environmentally toxic lithium batteries. These batteries must periodically be replaced, adding a radiological hazard for both safeguards inspectors and operators. An extended field test of these prototype PV energy harvesting (EH) RMSAs at an operational nuclear facility will give additional data and allow for an analysis of this technology in a variety of realistic conditions, which will be documented in a final report. RMSAs are used for this testing, but SNL envisions energy harvesting technology may be applicable to other safeguards equipment.

14 SOLAR ENERGY↗

Long-Range Development Framework

The Long-Range Development Framework (LRDF) guides effective, efficient, and sustainable land and infrastructure development for Sandia National Laboratories’ (SNL) New Mexico and California campuses. The LRDF is SNL’s seminal site planning document. Similar to a municipal planning document, it articulates a long-range development vision, framework goals, and a set of integrated development principles for land use, security, transportation, and environmental sustainability. The LRDF is neither a project planning document, nor does it recommend or eliminate specific projects; rather, it introduces planning concepts and provides guidance regarding effective, efficient, and sustainable site development.

99 GENERAL AND MISCELLANEOUS↗

System Engineering Applied: A Case Study in the Implementation of Successful Systems

The application of Systems Engineering (SE) principles has emerged to manage complex systems from a concept to the successful realization and implementation of the system. Multiple Research and Development (R&D) programs at Sandia National Laboratories (SNL) have implemented these principles and have maximized their efforts in the realization of successful systems. The Primary Standards Laboratory (PSL) at SNL has avoided the full implementation of such principles which has stalled the development of new and efficient calibration systems. The objective of this project is to introduce SE to the PSL and develop a framework of best practices that can be utilized to expedite the development and deployment of accurate and efficient testing systems throughout the PSL. A Case Study will be presented for the principles of the SE development lifecycle in a R&D environment to maximize the PSL’s efforts in a requirements-driven environment.

42 ENGINEERING↗

System Dynamics Modeling of the Colorado Basin for Optimizing Operations, Reducing Risk, and Increasing Resiliency

This paper is the output from SNL’s involvement in the Western Area Power Administration (WAPA), the Colorado River Energy Distributors Association (CREDA), and the Upper Colorado River Commission’s (UCRC) sponsored Phase II work to establish market and non-market values (NMV’s) of water and hydropower associated with Glen Canyon Dam (GCD) operations and the Colorado River ecosystem. It describes the purpose and need to develop a systems model for the Colorado River Basin that includes valuations in the economic, hydrologic, environmental, social, and cultural sectors. It outlines the benefits and unique features associated with such a model and provides a roadmap of how a systems model would be developed and implemented. While not meant to serve as a full development plan, the ideas and concepts herein represent what the Sandia National Laboratories (SNL) research team believes is the most impactful and effective path forward to address an ever increasing complex set of problems that occur at the basin-scale and beyond.

13 HYDRO ENERGY↗

Behavioral Health/Employee Assistance Program (EAP) Report FY 15

The Sandia National Laboratories’ (SNL) Corporate Behavioral Health Program is a workplace based program that 1) assists in the early identification and resolution of personal concerns which may impact job performance, 2) assists managers and the organization in addressing productivity issues, and 3) supports the SNL commitment to provide a safe and healthful work environment. The program is offered to approximately 10,711 employees in New Mexico. The Behavioral Health Program is a corporate program combining services in NM and CA. It is integrated with other occupational health and clinical services including disability, disease management and preventive health programs. In addition, Sandia’s Behavioral Health Program interfaces with external organizations in Human Resources, the Department of Energy and Security through the Clinical Evaluation (CE) Human Reliability Program (HRP) and Workplace Violence programs. The program supports Sandia National Laboratories’ mission to safeguard national security, the environment, the public and is a proactive approach to early identification, intervention and assessment. Last, it reduces barriers to accessing mental health services and assists with reducing health care costs attributed to illness or injuries related to unhealthy lifestyles and behaviors. The EAP team is comprised of a professional staff including a licensed Clinical Psychologist who has a NM state license for psychotropic medication prescriptive authority, is board certified in Clinical Neuropsychology, and a Certified Employee Assistance Professional (CEAP), a licensed professional clinical counselor NM State Licensed (LPCC) and a licensed Marriage and Family counselor (MFT) who is also a Certified Employee Assistance Professional and who holds a doctorate in counseling psychology.

99 GENERAL AND MISCELLANEOUS↗

Failures and Implications of Heat Pipe Systems

Under Department of Energy (DOE), Office of Nuclear Energy (NE), Gateway for Accelerated Innovation in Nuclear (GAIN), Sandia National Laboratories (SNL) was awarded DOE-NE GAIN voucher GA-19SN020107, "Risk-informed mechanistic source term calculations for a sodium fast reactor." Under this GAIN voucher, SNL supported the industry partners development in preparation for licensing and commercialization by providing subject matter expertise on heat pipe technologies, providing computer code training and support, and perform first-of-a-kind experiments demonstrating the safety/risk impacts of heat pipe breach failures. The experiments that were performed had two primary goals: measure the peak heat fluxes that lead to heat pipe dry out and subsequent wall breach; and observe the consequences that result from catastrophic failure of a heat pipe wall. Intentional breaching of the heat pipe walls took advantage of heat pipe physics and operating limits. Large and nearly instantaneous heat fluxes were applied to the heat pipe to first cause localized dry out at the evaporator section which then leads to melting of the heat pipe wall. The hour glass heat pipe (Test 1) experienced dry out at 112 W/cm 2 and after 45 seconds, wall temperatures measure about 1,280°C and intentional failure of the heat pipe wall was achieved. The cylindrical heat pipe (Test 2) experienced dry out at 125 W/cm 2 and after 65 seconds, wall temperatures exceeded 1,400°C and intentional failure of the heat pipe wall was achieved. Both experiments characterize the parameters needed to lead to heat pipe wall failure. Furthermore, the failure of the heat pipes characterizes the safety/risk impacts from sodium-oxygen reactions that occur following the intentional failure. There were two major conclusions of these intentional failure tests: the heat pipes were able to continue operating beyond expected performance limits, and the failure behavior validated decades of operational experience.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Tonopah Test Range Air Monitoring: CY2018 Meteorological, Radiological, and Wind Transported Particulate Observations

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This operation resulted in radionuclide-contaminated soils at the Double Tracks site and Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to the Clean Slate sites and at the TTR Sandia National Laboratories (SNL) Range Operations Center (ROC). The primary objective of the monitoring effort is to support the DOE Environmental Management Nevada Program (EM NV) in the safe remediation of the environmental legacy of nuclear device development and testing by determining if wind blowing across the Clean Slate sites is transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites, and to provide information for designing long-term monitoring of the sites. The monitoring program in 2018 included five stations. Station 400, located within TTR Area 3 and near the ROC, monitors conditions near the local workforce center. Stations 401 and 403 are located on the northern and southeastern perimeter fence lines, respectively, of the Clean Slate III site. Stations 404 and 405 are along the northern and eastern boundary fence, respectively, at Clean Slate II. The stations are generally downwind of the contaminated areas during either northwesterly or southerly winds, which are the predominant wind directions. The stations—which are similar in design to the Community Environmental Monitoring Program (CEMP) stations operating at locations surrounding the Nevada National Security Site and TTR—include meteorological instruments and continuous-flow, low-volume air samplers. Three pressurized ionization chambers for measuring gamma energy are in use at Stations 400, 401, and 403. Saltation sensors and saltation traps are deployed at the stations adjacent to the Clean Slate sites. Detailed meteorological data are recorded on data loggers, with periodic uploads via a satellite system to the Western Regional Climate Center (WRCC) at Desert Research Institute (DRI), to monitor instrument and site conditions. Air filter samples are collected every two weeks and the deposits in the saltation traps are collected when a sufficient sample mass for analysis has accumulated (generally a six- to eight-month interval). Monitoring at TTR in calendar year (CY) 2018 provided surveillance of both ambient conditions, and ground disturbance associated with remediation activities at Clean Slate II and III. The first half of CY2018 data from Stations 404 and 405 at Clean Slate II were collected during remediation activities at that site, and data collected during the final third of the year at Stations 401 and 403 at Clean Slate III coincided with remediation work at the site. Ambient conditions prevailed at Station 400 throughout the year. Dust transport by suspension and saltation is strongly dependent on wind speed. Concentrations of PM 10 (particulate matter of aerodynamic diameter ≤10 micrometers [μm], a size fraction of small particles that are suspended in the air and can be easily inhaled) remain low until winds exceed approximately 32 kilometers per hour (km/hr) (20 miles per hour [mph]). Saltation particle counts also increase above the same general threshold wind speed. Wind speeds in excess of 32 km/hr (20 mph) occur less than three percent of the time at the sites. Ground disturbing remediation activities were carried out at Clean Slate II from October 31, 2017, until July 26, 2018. Station 404 is located closest to the remediation area and is downwind of the area when winds are from the south. By late November, analysis of dust from the air sampler at Station 404 registered increases in plutonium-239+240 ( 239+240 Pu) concentrations. Peak plutonium concentrations, accompanied by elevated gross alpha concentrations and the detection of americium-241 ( 241 Am) by gamma spectroscopy, occurred between March and May 2018. During spring and early summer of 2018, elevated radionuclide concentrations were also measured in dust collected from the air sampler at Station 405, which is more than twice the distance from the remediation activity as Station 404. A minor but sustained increase in gross alpha concentration of suspended dust collected at Stations 400, 401, and 403 was also observed starting in May 2018 and continuing into August. Stations 401 and 403 are approximately 4.8 to 6.4 km (three to four miles) from Clean Slate II and Station 400 is approximately 13 km (eight miles) from that site. The radionuclide content of material that saltated into the passive Big Spring Number Eight (BSNE) traps during the Clean Slate II remediation period increased in both the traps facing toward and away from the fenced contamination area at Station 404, with the largest increases in concentration (almost five times the previous 239+240 Pu concentration) observed in the traps facing the fenced area. The radionuclide concentration in material in the trap facing away from the fence more than doubled from that measured in 2017. A similar increase was observed for the saltation trap facing away from the fenced area at Station 405, although no increase was observed for material captured in the trap facing the fenced area. Particles ranging in size from 50 to 500 µm generally move by saltation processes and are not expected to significantly contribute to dose for someone breathing in the standard respiratory zone for adult humans (1.5 to 1.7 m [4.9 to 5.6 ft] above ground level) because they are too large to be entrained in the air as suspended dust. Remediation activities at Clean Slate III began on September 5, 2018, and continued until a brief hiatus started on December 20, 2018. Although Station 401 is much closer to the remediation area than Station 403, the first increase in gross alpha and 239+240 Pu concentrations was noted in dust from filters collected at Station 403 in early November 2018. The highest radionuclide concentrations of 2018 at the Clean Slate III stations were recorded in air samples taken from Stations 401 and 403 in late December 2018 and these concentrations were comparable between the two station locations. Gamma rate data measured by the PICs was slightly higher than the annual average at Stations 401 and 403 after remediation activities began, but no single measurement was outside of the range observed in 2018 prior to remediation activities. No increase in radionuclide concentration was observed for the Clean Slate III remediation time period on air filters collected from the other stations. Radiological monitoring at Station 400—which is located at the ROC, and therefore the closest regularly staffed work location to the Clean Slate sites—recorded a higher mean gross alpha activity from dust collected on air sampler filters than in previous years. The individual biweekly air filters yielded measurements of gross alpha that were at or below the mean plus one standard deviation measured in CY2017, except for the period from April 25, 2018, through September 12, 2018. Nonetheless, gamma spectroscopy of all air filters from Station 400 identified only naturally occurring radionuclides, with no detection of americium-241 ( 241 Am) (which is used as an indicator of plutonium-241[ 241 Pu]). Alpha spectroscopy of selected air filters collected at Station 400 did not detect plutonium-238 ( 238 Pu) or 239+240 Pu above the analytical detection limit. Gross beta and gamma exposure rate data were comparable to data from regional CEMP stations. No saltation traps are deployed at Station 400. Considering the ambient monitoring periods during CY2018, the monitoring stations adjacent to the Clean Slate sites recorded above-background 238 Pu and 239+240 Pu concentrations (SNL, 1998; Turner et al., 2003) in samples collected by passive saltation traps and on selected air filters. These observations were consistent with previous years and indicated that radionuclide movement occurred under ambient conditions by processes of both saltation and suspension. The presence of radionuclides in all saltation traps, both upwind and downwind of the fenced contamination areas, was consistent with previous radiological survey results (EG&G, 1979) that show lower concentration radiologically contaminated material dispersed outside the fenced area. Although 239+240 Pu concentrations in the air filter samples were sometimes orders of magnitude higher than background, the concentrations were below risk-based action levels defined for an industrial area worker scenario (U.S. DOE, 2014). The interception of airborne dust with above-background radionuclide concentrations demonstrates that dispersal processes are continuing. Strong winds are the driver for both suspension and saltation of dust and soil. The recorded wind speed and PM10 during remediation activities at Clean Slate II and III identified discrete wind events lasting approximately five to eight hours each, which accounted for the greatest PM 10 concentrations at the monitoring stations. These events captured the effect of winds from the northwest and from the south. The observed differences in dust loading and radionuclide concentrations for the monitoring stations when they were either upwind or downwind of the contamination area identify the remediation area as a source of plutonium contaminated dust. The increase in concentration of radionuclides in airborne dust during the remediation activities, compared with measurements under previous ambient conditions (mean 239+240 Pu concentrations during remediation activities are approximately nine to 40 times higher compared to pre-remediation concentrations, depending on monitoring station), highlights the impact of land disturbance on wind-borne contaminant transport from the Clean Slate test areas. The meteorological and particulate matter monitoring indicated that conditions for wind-borne contaminant movement exist at the Clean Slate sites, and that transport of radionuclide-contaminated soil by both suspension and saltation occurred under ambient conditions and accelerated when the sites were disturbed. The 239+240 Pu alpha spectroscopy results indicated that airborne concentrations during remediation activities ranged from 2 × 10-16 to 380 × 10-16 µCi/ml. These results can be compared to the derived air concentration limit for 239 Pu of 6 × 10-11 µCi/ml for occupational workers contained in Code of Federal Regulations 10 CFR 835, Occupational Radiation Protection. Even though the air sampling results document an increase in concentration during remediation activities, the observed concentrations are less than 0.06 percent of the occupational limit. The Corrective Action Unit (CAU) closure strategy uses a risk-based approach, whereby acceptable contaminant concentrations are determined as a function of anticipated human exposure.

54 ENVIRONMENTAL SCIENCES↗

Electrical Arc Fault Particle Size Characterization

In this investigation a series of small-scale tests were conducted, which were sponsored by the Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) and performed at Sandia National Laboratories (SNL). These tests were designed to better understand localized particle dispersion phenomena resulting from electrical arcing faults. The purpose of these tests was to better characterize aluminum particle size distribution, rates of production, and morphology (agglomeration) of electrical arc faults. More specifically, this effort characterized ejected particles and high-energy dispersion, where this work characterized HEAF electrical characteristics, particle movement/distributions, and morphology near the arc. The results and measurements techniques from this investigation will be used to inform an energy balance model to predict additional energy from aluminum involvement in the arc fault. The experimental setup was developed based on prior work by KEMA and SNL for phase-to-ground and phase-to-phase electrical circuit faults. The small-scale tests results should not be expected to be scale-able to the hazards associated with full-scale HEAF events. Here, the test voltages will consist of four different levels: 480V, 4160V, 6900V and 10kV, based on those realized in nuclear power plant (NPP) HEAF events.

36 MATERIALS SCIENCE↗

Energy Harvesting Remotely Monitored Sealing Array (RMSA) (Field Test Annual Report)

Sandia National Laboratories (SNL) is investigating photovoltaic (PV) cell configurations, integrating them with the battery-operated Remotely Monitored Sealing Array (RMSA), and testing and evaluating performance for enhanced battery life under various lighting conditions at a facility at the Savannah River Site (SRS) or Savannah River National Laboratory (SRNL). Unattended safeguards equipment (e.g. seals) incorporates many low-power electronic circuits, which are often powered by expensive and environmentally toxic lithium batteries. These batteries must periodically be replaced, adding a radiological hazard for both safeguards inspectors and operators. An extended field test of these prototype PV energy harvesting (EH) RMSAs at an operational nuclear facility will give additional data and allow for an analysis of this technology in a variety of realistic conditions, which will be documented in a final report. RMSAs are used for this testing, but SNL envisions energy harvesting technology may be applicable to additional safeguards equipment.

14 SOLAR ENERGY↗

Final Letter Report for AEgis Technologies NMSBA Project

This letter report signals the end of the NMSBA project to help AEgis Technologies (AEGis) find a way to solve a coupled heat transfer equation for a laser-heated Silicon wafer. Accompanying this letter report is a MATLAB live script that documents the work done to date and provides a first attempt at a solution. The scope of work provided for Sandia National Laboratories (SNL) to document the problem in a general form in this phase of the work, with the goal of applying for additional funding in Calendar Year 2020 to attempt a complete solution. SNL staff analytically solved the differential heat equation and found solutions that reproduce reasonable shapes for heat flux. However, the required information to provide a complete solution is not available.

97 MATHEMATICS AND COMPUTING↗

Shaker Table Test

This report describes the Shaker Table Test conducted on September 12, 2018, at the Dynamic Certification Laboratories (DCL) in Sparks, Nevada. This report satisfies Milestone M3SF-19SN010202021 Shaker Table Test, Sandia National Laboratories (SNL) Work Package (Parent WBS # 1.08.01.02.02; Work Package #SF-19SN01020202). The Shaker Table Test is related to the Multi-Modal Transportation Test (MMTT) conducted in 2017. During the MMTT, accelerations and strains were measured on the transportation platform, ENsa UNiversal (ENUN) 32P dual-purpose rail cask, cradle, basket, and three surrogate 17x17 pressurized water reactor (PWR) assemblies (one from SNL, one from Spain and one from Korea).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗