Track 5: Radioisotope Power Systems

Paper and Podium Presentation

AuthorsTitle
1G. RomanoskiAN INVESTIGATION OF THE RHEOLOGICAL BEHAVIOR OF PHENOLIC RESINS CONSIDERED FOR PRODUCTION OF CARBON BONDED CARBON FIBER INSULATION
2R. M. Wham, R. Steve Owens, J. H. Miler, S. PierceAUTOMATION OF NEPTUNIUM OXIDE–ALUMINUM TARGET FABRICATION
3J. McduffeeDESIGN AND ANALYSIS OF A NPO2 TARGET FOR THE PRODUCTION OF PU238
4J. Hong, K. Son, J. Kim, J. KimDESIGN OF ETG FOR LOW ORBIT TEST OF THE KOREA LAUNCH VEHICLE
5C. DailyDESIGN OPTIMIZATION STUDIES FOR NPO2 TARGETS IRRADIATED IN THE HIGH FLUX ISOTOPE REACTOR
6A.DEVELOPMENT OF THE PLUTONIUM MODELING AND ASSESSMENT (PUMA) SIMULATION THROUGH THE COUPLING OF EXPERIMENTS AND MOLECULAR DYNAMICS
7C. E. Whiting, D. P. Kramer, C. D. BarklayEMPIRICAL POWER PREDCITION FOR MMRTG F1
8N. GallegoEVALUATION OF ALTERNATIVE FIBERS TO REPLACE NARC-RAYON FOR THE PRODUCTION OF CBCF
9J. TeagueIMPACT TEMPERATURE DETERMINATION FOR GPHS SAFETY TESTING
10D. Chandler, M. W. Crowell, K. E. RoystonINCREASED PLUTONIUM-238 PRODUCTION VIA HIGH FLUX ISOTOPE REACTOR PERMANENT BERYLLIUM REFLECTOR REDESIGN
11K. G. Myhre, M. E. Woods, A. J. Unger, P. D. Benny, D. E. Benker, E. D. Collins, L. H. Delmau, D. W. Depaoli, F. D. Riley, R. M. WhamINITIAL TESTING OF MEDIATED ELECTROCHEMICAL OXIDATION FOR INCLUSION IN THE PLUTONIUM-238 PRODUCTION PROGRAM
12D. Lonnie JohnsonJOHNSON THERMO-ELECTROCHEMICAL CONVERTER (JTEC) AS A HEAT TO ELECTRIC GENERATOR FOR NUCLEAR POWER SYSTEMS
13D. KramerMIXED ALUMINA/CERIA COMPOSITIONS AS AN ENHANCED CERAMIC PROCESSING SURROGATE FOR RPS FUEL PELLETS
14L. HawkinsMODELING HELIUM AND OXYGEN BEHAVIOR OF A PLUTONIA PELLET IN AN MMRTG
15R. HowardOVERVIEW OF THE PLUTONIUM-238 SUPPLY PROGRAM’S CERMET PRODUCTION TARGET
16F. Anne CarverPARTICLE SIZE ANALYSIS OF CERIUM DIOXIDE SURROGATE MATERIALS AS A SIMULANT FOR PLUTONIUM-238 DIOXIDE FUELS PROCESSING
17J. RockPATH TO A NEXT GENERATION RADIOISOTOPE THERMOELECTRIC GENERATOR (RTG)
18D. DepaoliPROCESS DEVELOPMENT FOR PLUTONIUM-238 PRODUCTION AT OAK RIDGE NATIONAL LABORATORY
19R. Miller, B. Friske, K. R. Veach, JrQUALIFICATION OF SPECIAL PROCESSES USING A GRADED APPROACH FOR THE LIGHT-WEIGHT RADIOISOTOPE HEATER UNIT METALLIC COMPONENT PRODUCTION AT OAK RIDGE NATIONAL LABORATORY
20T. J. SutliffRADIOISOTOPE POWER SYSTEMS - AN INTERAGENCY PROGRAM STATUS
21K. Rex Veach, Jr.RE-ESTABLISHMENT OF LIGHT-WEIGHT RADIOISOTOPE HEATER UNIT PLATINUM-30% RHODIUM ALLOY COMPONENTS PRODUCTION AT OAK RIDGE NATIONAL LABORATORY
22K. Kazemzadeh, J. MccoyTHE DEVELOPMENT, PROTOTYPING AND TESTING OF A SHOCK TOLERANT MILLI-WATT RADIOISOTOPE POWER SYSTEM

Lightning Talk

AuthorsTitle
1B. Skidmore, H. A. Quintana, A. J. Parkison, L. B. Davenhall, K. D. AbneyAM-241 OXIDE PRODUCTION AT LOS ALAMOS NATIONAL LABORATORY
2L.BETAVOLTAICS FROM COTS: POWER FOR YEARS
3J. KatalenichCONCEPTUAL DESIGN OF A HIGH POWER DENSITY HEAT SOURCE MODULE
4C. PerezIMPROVING POWER FACTOR AND MECHANICAL PROPERTIES OF YB14MGSB11 FOR APPLICATION IN A RADIOISOTOPE THERMAL GENERATOR.
5J. KatalenichOBSERVATIONS OF AGING 238PUO2 MICROSPHERES
6G. MarcantelOPTIMIZATION OF PLUTONIUM-238 PRODUCTION IN THE ADVANCED TEST REACTOR FOR RADIOISOTOPE THERMOELECTRIC GENERATORS IN DEEP SPACE EXPLORATION APPLICATIONS
7J. NavarroORNL-INL DATA DRIVEN OPTIMIZATION PRODUCTION AND HARVESTING TOOL
8C. BryanPOTENTIAL IMPROVEMENTS TO 237NP TARGETS AT THE HIGH FLUX ISOTOPE REACTOR
9M. B. R. SmithTHE RADIOISOTOPE POWER SYSTEM DOSE ESTIMATION TOOL (RPS-DET) 2019 DEVELOPMENT UPDATE

Paper and Podium Presentation

AN INVESTIGATION OF THE RHEOLOGICAL BEHAVIOR OF PHENOLIC RESINS CONSIDERED FOR PRODUCTION OF CARBON BONDED CARBON FIBER INSULATION

G. Romanoski romanoskigr@ornl.gov
Carbon Bonded Carbon Fiber Insulation is made from chopped and carbonized rayon fibers bonded by carbonized phenolic resin. The rheological behavior of several resins was investigated to determine if alternative resins would be more effective in forming carbon-bond precursors.
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AUTOMATION OF NEPTUNIUM OXIDE–ALUMINUM TARGET FABRICATION

R. M. Wham, R. Steve Owens, J. H. Miler, S. Pierce whamrm@ornl.gov
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DESIGN AND ANALYSIS OF A NPO2 TARGET FOR THE PRODUCTION OF PU238

J. Mcduffee mcduffeej@ornl.gov
Current production of Pu-238 at Oak Ridge National Laboratory uses NpO2aluminum cermet pellets as the feed material. The advantage of cermet is that its thermal conductivity is much higher than that of the oxide alone, which greatly reduces pellet temperatures. However, the melting point of the material is quite low due to the aluminum in the matrix, and the recovery of the Pu-238 results in substantial radioactive liquid waste. There is potentially both a significant production gain and a reduction in post-irradiation processing cost and waste associated with using a pure NpO2 pellet. This work describes ongoing efforts to design a NpO2 pellet to maximize production of Pu-238 in the High Flux Isotope Reactor.
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DESIGN OF ETG FOR LOW ORBIT TEST OF THE KOREA LAUNCH VEHICLE

J. Hong, K. Son, J. Kim, J. Kim jthong@kaeri.re.kr
Korea Aerospace Research Institute will launch a satellite for a low-orbit test of the Korea Launch Vehicle in 2021. An electrically heated thermoelectric generator (ETG) with mass of 850 g will be one of its payloads. To assure the design heritage and the reliability of the ETG in the space environment, a small ETG will be tested at the top of the satellite for more than a year. In this study, an ETG with 10 W of heat input was designed through simulations such as heat transfer analysis, modal analysis, thermoelectric analysis, and structural analysis. In addition, a mockup was fabricated and basic performance tests were carried out.
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DESIGN OPTIMIZATION STUDIES FOR NPO2 TARGETS IRRADIATED IN THE HIGH FLUX ISOTOPE REACTOR

C. Daily dailycr@ornl.gov
Efforts to re-establish a domestic 238Pu production capability in support of National Aeronautics and Space Administration (NASA) mission objectives are ongoing throughout the US Department of Energy (DOE) complex. Design and optimization studies of 237Np-bearing targets are underway at Oak Ridge National Laboratory (ORNL). It is anticipated that targets will be irradiated in ORNLs High Flux Isotope Reactor (HFIR) and in the Advanced Test Reactor at Idaho National Laboratory. A variety of target materials, containments, arrangements, and irradiation histories have been analyzed, and the results indicate that a sufficient quantity of 238Pu can be produced in HFIR to fulfill NASAs current mission objectives. This paper focuses on the design and optimization of new target configurations containing pellets that are (1) 92% 2% of the theoretical density (TD) of NpO2, (2) loaded into pins of cladding materials that can be handled as solid waste following post-irradiation 238Pu recovery operations, (3)irradiated in various vertical experiment facility (VXF) locations in the HFIR permanent beryllium reflector, and (4) rotated within and/or moved to another VXF location following each HFIR operational cycle to maximize 238Pu production and minimize peak heat generation rates.
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DEVELOPMENT OF THE PLUTONIUM MODELING AND ASSESSMENT (PUMA) SIMULATION THROUGH THE COUPLING OF EXPERIMENTS AND MOLECULAR DYNAMICS

A. ajparkison@lanl.gov
A finite element computer simulation has been developed at the Los Alamos National Laboratory (LANL) to simulate the production process of 238PuO2 heat source pellets. This simulation, the Plutonium Modeling and Assessment (PUMA) code, is built upon the MOOSE framework. It was developed through an extensive experimental campaign using surrogates and validated for use in the PuO2 system through molecular dynamics simulations. The PUMA code is currently being used at LANL to understand and improve upon the current fabrication process.
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EMPIRICAL POWER PREDCITION FOR MMRTG F1

C. E. Whiting, D. P. Kramer, C. D. Barklay chris.whiting@udri.udayton.edu
Power predictions for the MMRTG are, in part, based off of early performance data for the MMRTG F1 unit, currently on Mars. Now that F1 has been in operation for over half of its design life, a detailed analysis of its performance can be obtained. In this paper, a power degradation curve was made using the F1 telemetry data. Upon analysis of the data, it was determined that the power degradation does not obey first-order kinetics, and a much higher order rate equation was derived. This empirical degradation curve and rate equation can then be used to predict the performance of F1 for the remaining 7 years of its design life. These empirical predictions indicate that at the end of design life, F1 will be producing 75.2 We. This is a 25% increase in power over earlier predictions. A conservative estimate for future MMRTG performance indicates that the minimum power at the end of design life is 72.8 We. This is a 32% increase in power over earlier predictions. Communicating this improvement in the power prediction is important so that future science missions can plan to appropriately make use of the power that MMRTG will provide. In addition, it may be useful to communicate to the community the fact that the power degradation of MMRTG is steadily decreasing with time. Using a fixed annual power degradation value will not accurately describe the behavior of the MMRTG power.
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EVALUATION OF ALTERNATIVE FIBERS TO REPLACE NARC-RAYON FOR THE PRODUCTION OF CBCF

N. Gallego gallegonc@ornl.gov
A unique Carbon Bonded Carbon Fiber (CBCF) insulation was developed to provide thermal protection to the isotopic fuel in Radioisotope Power Systems. The microstructure of CBCF is comprised of chopped and carbonized rayon fibers bonded at intersections by carbonized phenolic resin. Production of CBCF insulation at ORNL has been sustained for the past three decades by a single lot of rayon purchased from North American Rayon Corporation (NARC) of Elizabethton, TN in 1987. NARC ceased operations in 1996. Although ORNL has a seven-to-ten-year supply of rayon at the current rate of consumption, an effort has been initiated to identify a new source to meet long-range needs. A summary of findings from the ongoing search for a fiber to replace NARC rayon for production of CBCF is presented.
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IMPACT TEMPERATURE DETERMINATION FOR GPHS SAFETY TESTING

J. Teague mulford@lanl.gov
Impact Testing of General Purpose Heat Sources (GPHS) is done to benchmark extensive safety calculations quantifying launch safety. Efforts to conduct an impact test at the extreme low end of the temperature range for launch highlights uncertainties in determining the GPHS clad temperature during impact tests. Direct measurement of clad temperatures in the impact configuration are described, and the effect of emissivity of the various components indicated. Calculation of the experimental clad impact temperature using the ANSYS thermal transport model indicates that the clad temperature at impact was outside the relevant range for launch safety modelling of GPHS behavior.
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INCREASED PLUTONIUM-238 PRODUCTION VIA HIGH FLUX ISOTOPE REACTOR PERMANENT BERYLLIUM REFLECTOR REDESIGN

D. Chandler, M. W. Crowell, K. E. Royston chandlerd@ornl.gov
Irradiation of 237Np-bearing targets in the permanent beryllium reflector (PBR) of Oak Ridge National Laboratorys (ORNL) High Flux Isotope Reactor (HFIR) results in high-purity 238Pu that can be used as a reliable power source for deep space and planetary National Aeronautics and Space Administration missions. However, HFIRs 238Pu production capability is constrained by the available irradiation volume in its PBR. In preparation for the HFIR beryllium change-out in 2023, ORNL staff have redesigned the PBR to include six additional irradiation sites, be more versatile with respect to irradiation and scattering experiments, and enhance its thermal-structural performance. The new PBR design offers large potential increases in annual 238Pu production at ORNL.
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INITIAL TESTING OF MEDIATED ELECTROCHEMICAL OXIDATION FOR INCLUSION IN THE PLUTONIUM-238 PRODUCTION PROGRAM

K. G. Myhre, M. E. Woods, A. J. Unger, P. D. Benny, D. E. Benker, E. D. Collins, L. H. Delmau, D. W. Depaoli, F. D. Riley, R. M. Wham myhrekg@ornl.gov
Oak Ridge National Laboratory is currently restarting the United States capability to produce kilogram quantities of 238 Pu annually for space power applications. This involves the purification of 238 Pu from neutron-irradiated 237 Np targets. Plutonium oxide is produced at various points during the radiochemical processing of these irradiated 237 Np targets, including as a final product for shipment to Los Alamos National Laboratory. Dissolution of the plutonium oxide product material is required to obtain an isotopic assay and impurity analysis of the product material. An electrochemical method that produces highly oxidizing ions in solution is currently being investigated as a rapid method for dissolving these plutonium oxide samples.
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JOHNSON THERMO-ELECTROCHEMICAL CONVERTER (JTEC) AS A HEAT TO ELECTRIC GENERATOR FOR NUCLEAR POWER SYSTEMS

D. Lonnie Johnson bprokes@johnsonrd.com
The Johnson-Thermo-Electrochemical Converter (JTEC) is a solid state heat engine that has the potential for achieving energy conversion efficiency levels as high 30 to 40% net, 70 to 80% of Carnot. Over the past five decades, conventional thermoelectric converters (Seebeck) have only achieved efficiency levels less than 15% of Carnot (6% net). As a more efficiency replacement for conventional converter technology, JTEC will provide NASA an attractive alternative for addressing the ever present need to minimize the amount of mass that must be delivered to space using expensive launch vehicles. A laboratory proof of concept demonstration has been successfully completed and an initial application analyses has been performed to understand the technology and its potential impacts at maturity. Johnson Research in collaboration with John Hopkins Applied Physics Laboratory are starting a program under the Radioisotope Power Systems Program to further explore the concept and advance the technology.
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MIXED ALUMINA/CERIA COMPOSITIONS AS AN ENHANCED CERAMIC PROCESSING SURROGATE FOR RPS FUEL PELLETS

D. Kramer daniel.kramer@udri.udayton.edu
Due to various safety and other considerations, the U.S. currently employs plutonium-238in the form of 238PuO2 ceramic pellets as the fuel source in its current RPS (Radioisotope Power System) design. It is anticipated that a future European RPS design will also utilize a ceramic fuel form, such as 241AmO2-x. Understanding the processing characteristics of the selected ceramic fuel form is one technical subject common to both efforts. While it would be ideal to perform RPS fuel processing experiments with the actual heat source radioisotope, due to radiological, cost, materials availability, and other considerations the employment of a non-hazardous and non-radioactive surrogate material could greatly ease this field of study. Identifying a cold surrogate material, that as closely as possible mimics the processing characteristics of the selected radioisotope, will enhance future development studies in support of both European and U.S. RPS activities. This paper centers on the recent application of mixed alumina/ceria compositions as an enhanced ceramic processing surrogate in support of both respective RPS programs.
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MODELING HELIUM AND OXYGEN BEHAVIOR OF A PLUTONIA PELLET IN AN MMRTG

L. Hawkins lhawk1124@yahoo.com
The PuO2 pellets in the Multi-mission Radioisotope Thermoelectric Generator (MMRTG) were studied to understand the thermal, chemical and diffusion properties of the internally produced gases, to mitigate material interactions during the mission. Helium gas, produced from the alpha decay of the plutonium, and oxygen ions, produced by the reduction reaction of the PuO2, were modeled in COMSOL to demonstrate the behavior as the gases escape from the pellet. Helium and oxygen ions were produced by internal reactions which diffused through the grains. The thermal model produced an approximately 92 K temperature gradient from the centerline of the pellet to the surface. The physical properties of both elements were temperature dependent, and models were made for each depending on the rate of diffusion and permeation. The helium model of the open porosity demonstrated a higher pressure in the center, with a pressure gradient of approximately 0.065 Pa to the surface. The oxygen model showed the difference between two sizes of grains in the pellet, taking approximately 0.07 s to diffuse to the grain boundary for a 10 ?m grain and approximately 1.65 s for a 50 ?m grain. However, inaccuracies of this model resulted from the use of the diffusion coefficient of oxygen gas, and not that of an oxygen ion. A more accurate model can be produced with the correct diffusion coefficient.
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OVERVIEW OF THE PLUTONIUM-238 SUPPLY PROGRAM’S CERMET PRODUCTION TARGET

R. Howard howardrh@ornl.gov
The Plutonium-238 Supply Program is tasked with establishing a reliable domestic supply of Pu-238 to fuel radioisotope thermal generators and its role in supporting future space exploitation is crucial. In order to meet this need, researchers at the Oak Ridge National Laboratory developed a robust production target design that is used to irradiate neptunium/aluminum cermet pellets to transmute the feedstock into the usable Pu-238. This paper describes this target design, and the innovative design features employed to improve target fabrication and assembly.
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PARTICLE SIZE ANALYSIS OF CERIUM DIOXIDE SURROGATE MATERIALS AS A SIMULANT FOR PLUTONIUM-238 DIOXIDE FUELS PROCESSING

F. Anne Carver fcarver@lanl.gov
Failure attributed to pellet cracking during fabrication of 238PuO2 pellets places a severe burden on production efforts through lost time, increased radiation dose due to product rework, and supplementary costs. Unfortunately, the difficulty in working with this material makes identification of root causes, and subsequent correction, infeasible on the production floor. Furthermore, the work presented here begins to experimentally investigate the behavior and variable sensitivity of the grog feedstock at the front end of the pellet production process using CeO2 surrogate material. This information is critical for establishing a baseline for the grog feedstock, one of the key variables in defining the performance of a 238PuO2 pellet during fabrication. Looking forward, this analysis lays the foundation for continued study and training using non-surrogate PuO2 materials.
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PATH TO A NEXT GENERATION RADIOISOTOPE THERMOELECTRIC GENERATOR (RTG)

J. Rock Jennifer.l.rock@nasa.gov
The Next Generation RTG Project (Next Gen RTGP) is one of three NASA-led projects commissioned by the Radioisotope Power Systems (RPS) Program. NASA HQ created the RPS Program in 2009 to ensure investments made in RPS technologies and systems would best meet future mission needs. As commissioned by the RPS Program, the main objective of the Next Gen RTGP is to mature an RPS technology and transition it to a new vacuum rated flight system design to ultimately allow DOE to fuel and deploy the Next Gen RTG for NASA mission needs for a non-atmosphere power solution. The Next Gen RTGP is offering system designers access to thermoelectric research previously conducted within the RPS Program as a potential energy conversion technology to meet that objective. The Next Gen RTGP works with DOE to provide system design contracts, and leverages an interagency partnership between the RPS Program and the DOE Office of Nuclear Energy to provide technically feasible power system solutions. The contracts are through Idaho National Laboratory (INL).
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PROCESS DEVELOPMENT FOR PLUTONIUM-238 PRODUCTION AT OAK RIDGE NATIONAL LABORATORY

D. Depaoli depaolidw@ornl.gov
The third chemical processing campaign conducted at Oak Ridge National Laboratory with irradiated neptunium oxidealuminum cermet targets produced plutonium-238 oxide product meeting purity specifications for space power applications. This is a major step for the Plutonium?238 Supply Program toward reestablishing production. This summary highlights results to date and presents focus areas of current activities to improve process efficiency and to increase production rate.
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QUALIFICATION OF SPECIAL PROCESSES USING A GRADED APPROACH FOR THE LIGHT-WEIGHT RADIOISOTOPE HEATER UNIT METALLIC COMPONENT PRODUCTION AT OAK RIDGE NATIONAL LABORATORY

R. Miller, B. Friske, K. R. Veach, Jr millerrg@ornl.gov
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RADIOISOTOPE POWER SYSTEMS - AN INTERAGENCY PROGRAM STATUS

T. J. Sutliff tsutliff@nasa.gov
Radioisotope power systems (RPS) have been in use in the United States for over 50 years. RPS-enabled NASA missions have utilized space nuclear power allowing them to explore planets, moons, and interstellar space. This exploration resulted in changes to our understanding of our Solar System and our place within it. In 2009, NASA HQ created a NASA program to ensure investments made in RPS technologies and systems would be best utilized by future missions. The RPS Program seeks to ensure the availability of RPS for the exploration of the solar system in environments where conventional solar or chemical power generation is impractical or impossible. The RPS Program, in partnership with the DOE Office of Nuclear Energy began, and continues to operate as an interagency partnership to provide technologically robust power system solutions to robotic spacecraft and exploration missions that otherwise would not be feasible. This paper provides a synopsis of current activities after a decade of formal interagency partnering.
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RE-ESTABLISHMENT OF LIGHT-WEIGHT RADIOISOTOPE HEATER UNIT PLATINUM-30% RHODIUM ALLOY COMPONENTS PRODUCTION AT OAK RIDGE NATIONAL LABORATORY

K. Rex Veach, Jr. rveach2662@gmail.com
During FY2018 the Oak Ridge National Laboratory (ORNL) Radioisotope Power Systems (RPS) Program completed re-establishment of capability to produce platinum-30% rhodium (Pt-30Rh) alloy components for the Light Weight Radioisotope Heater Unit (LWRHU) Program. These components were last produced at Mound Laboratory in the mid/late-1990s for the National Aeronautics and Space Administration (NASA) Cassini mission. The LWRHU Pt-30Rh Clad Body Subassembly and component fabrication operations are being performed in the iridium alloy Clad Vent Set (CVS) production area at ORNL. Existing equipment (furnaces, electron beam welders, presses, inspection, etc.) are being utilized along with new equipment (two lathes and laser marker) that were purchased for this work. ORNL purchased and qualified an initial quantity of starting materials (Pt powder, Pt-30Rh foil, sheet, and tubing). Equipment, tooling, and materials were procured/fabricated and qualified. Drawings and specifications were updated/modified/developed to the ORNL RPS Program format. Procedures were developed and qualified. All drawings, specifications, and procedures were reviewed/approved by the Idaho National Laboratory (INL) RPS Lead Lab Document Configuration Control Board (DCCB). The dimensional inspection operations and special processes (cleaning, heat treating, sintering, dye penetrant inspection, leak testing, and welding) were successfully qualified and documented. This paper will discuss the process of re-establishing LWRHU production at ORNL to provide for future NASA space exploration science mission needs10.
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THE DEVELOPMENT, PROTOTYPING AND TESTING OF A SHOCK TOLERANT MILLI-WATT RADIOISOTOPE POWER SYSTEM

K. Kazemzadeh, J. Mccoy k.kazemzadeh@hi-z.com
Hi-Z Technology, Inc. has recently built, developed and tested a new milliwatt radioisotope power system (mW-RPS) after more than a decade of dormancy. Using a single 1.1Wt radioisotope heater unit (RHU), it will provide steady electric power of about 35 mW at 5 volts while also providing heat to the surrounding system components. Recent work has improved and validated the impact tolerance of the device. Development continues toward flight readiness.
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AM-241 OXIDE PRODUCTION AT LOS ALAMOS NATIONAL LABORATORY

B. Skidmore, H. A. Quintana, A. J. Parkison, L. B. Davenhall, K. D. Abney bes@lanl.gov
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BETAVOLTAICS FROM COTS: POWER FOR YEARS

L. lance.hubbard@pnnl.gov
Overwhelmingly, betavoltaics (BV) long-lasting power opens a broad range of applications which are not currently available. The birth of very low power electronics has opened up a market for the wide and accepted use of BVs (US Patent: US9887018). Todays low-power electronics are feeding the internet of things revolution. We propose to develop a low-power demonstration to support basic science studies in efficiency, component damage, and manufacturing processing of betavoltaic devices. Beta particle impacts have the potential to damage the metal contact region of the betavoltaic device. Beta particles impact in the region where power is extracted from the semiconductor, this electron-hole pairs made by the beta can promote the formation of metal alloys at the extraction point which leads to lost power generation. The formation of intermetallic contact alloys by beta impacts is not well known and can lead to device inoperability. The formation of beta-induced alloys at the contacts of the betavoltaic needs to be understood for the next generation of semiconductors. This work will seek to understand the formation of intermetallic regions at the contacts, as well as propose possible mitigation strategies. A better understanding of contact intermetallic formation from betavoltaics will set PNNL up as a world leader in this field and lead to development of PNNL based betavoltaic power for mission-critical sensor platforms.
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CONCEPTUAL DESIGN OF A HIGH POWER DENSITY HEAT SOURCE MODULE

J. Katalenich jakatale@gmail.com
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IMPROVING POWER FACTOR AND MECHANICAL PROPERTIES OF YB14MGSB11 FOR APPLICATION IN A RADIOISOTOPE THERMAL GENERATOR.

C. Perez cpe@ucdavis.edu
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OBSERVATIONS OF AGING 238PUO2 MICROSPHERES

J. Katalenich jakatale@gmail.com
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OPTIMIZATION OF PLUTONIUM-238 PRODUCTION IN THE ADVANCED TEST REACTOR FOR RADIOISOTOPE THERMOELECTRIC GENERATORS IN DEEP SPACE EXPLORATION APPLICATIONS

G. Marcantel gracemarcantel16@gmail.com
Plutonium production for use in Radioisotope Thermoelectric Generators (RTGs) is becoming increasingly important in the United States due to several reasons. The plutonium stockpile originally purchased from the USSR has steadily decreased due to utilization in RTGs and the degrading quality of the specific plutonium isotope of interest in the stockpile: plutonium-238. With a half-life of 87.7 years, the quality has decreased since it was originally purchased just after the Cold War. The United States is aiming to produce high-quality 238Pu and become independent in space fuel production in the process. The high-quality plutonium combined with the currently available low-quality plutonium will produce usable fuel for future space explorations like the Mars 2020 expedition. This paper details the new models / methodologies investigated by Center for Space Nuclear Research (CSNR) to optimize 238Pu production in the Advanced Test Reactor (ATR). Increasing the 238Pu production at ATR will supplement the current production at the High Flux Isotope Reactor (HFIR) at Oak Ridge National Labs in Tennessee to achieve the national goal of 1.5 2.0 kg 238Pu per year.
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ORNL-INL DATA DRIVEN OPTIMIZATION PRODUCTION AND HARVESTING TOOL

J. Navarro navarroj@ornl.gov
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POTENTIAL IMPROVEMENTS TO 237NP TARGETS AT THE HIGH FLUX ISOTOPE REACTOR

C. Bryan bryancd@ornl.gov
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THE RADIOISOTOPE POWER SYSTEM DOSE ESTIMATION TOOL (RPS-DET) 2019 DEVELOPMENT UPDATE

M. B. R. Smith smithmb@ornl.gov
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