"Post-irradiation examination of UN-Mo-W fuels for space nuclear propulsion" Jason L. Schulthess, Indrajit Charit, Aaron Craft, William Chuirazzi, Jatuporn Burns, David Frazer, Nicolas Woolstenhulme, Robert O'Brien, Sarah A. Khan, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155476 · ISSN: 0022-3115 | |
"Orientation-selected micro-pillar compression of additively manufactured 316L stainless steels: Comparison of as-manufactured, annealed, and proton-irradiated variants" Cheng Sun, Michael McMurtrey, Robert O'Brien, Frank A. Garner, Lin Shao, Ching-Heng Shiau, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153739 · ISSN: 0022-3115 | |
"Options for Subscale Maturation of Advanced Reactor Technologies Testing for Nuclear Thermal Propulsion" Katey Lenox, Robert O'Brien, Isabella Rieco, Kelsa Palomares, William Searight, Michael Todosow, James Werner, Douglas Burns, [2022] · DOI: 10.2172/1844192 | |
"Atomic layer deposited boron nitride nanoscale films act as high temperature hydrogen barriers" Theodore A. Champ, Sai V. Raj, Robert C. O'Brien, Charles B. Musgrave, Alan W. Weimer, Sarah K. Bull, [2021] Applied Surface Science · DOI: 10.1016/j.apsusc.2021.150428 · ISSN: 0169-4332 | |
"Deformation behavior and irradiation tolerance of 316 L stainless steel fabricated by direct energy deposition" Michael D. McMurtrey, Robert C. O'Brien, Nathan D. Jerred, Randall D. Scott, Jing Lu, Xinchang Zhang, Yun Wang, Lin Shao, Cheng Sun, Ching-Heng Shiau, [2021] Materials and Design · DOI: 10.1016/j.matdes.2021.109644 · EID: 2-s2.0-85103104832 · ISSN: 1873-4197 | |
"Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility" C. Sun, R.E. Rupp, C.-H. Shiau, R. Hanbury, N. Jerred, R. O'Brien, M. McMurtrey, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152739 · EID: 2-s2.0-85098056865 · ISSN: 0022-3115 | |
"Atomic layer deposition of tungsten nitride films as protective barriers to hydrogen" W. Wilson McNeary, Cynthia A. Adkins, Theodore A. Champ, Chanel A. Hill, Robert C. O'Brien, Charles B. Musgrave, Alan W. Weimer, Sarah K. Bull, [2020] Applied Surface Science · DOI: 10.1016/j.apsusc.2019.145019 · ISSN: 0169-4332 | |
"High-temperature, heat pipe-cooled, fast micro-reactor concept using stainless steel and uranium oxide fuel elements" [2019] PBNC 2018 - Pacific Basin Nuclear Conference | |
"Preliminary Assessment of Two Alternative Core Design Concepts for the Special Purpose Reactor" James E. Werner, Andrew J. Hummel, John C. Kennedy, Robert C. O'Brien, Axel M. Dion, Richard N. Wright, Krishnan P. Ananth, James W. Sterbentz, [2018] · DOI: 10.2172/1466790 | |
"Quantitative crack analysis using neutron radiography with gadolinium contrast enhancement agents" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062990051 · ISSN: 0003-018X | |
"Controlled relative humidity storage for high toughness and strength of binderless green pellets"
Rita E. Hoggan, Arnold Erickson, Bryan Forsmann, Robert C. O'Brien, Paul A. Lessing, W. Roger Cannon,
[2017]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.14982
· EID: 2-s2.0-85029623394
· ISSN: 1551-2916
An equation was developed to predict fracture toughness of green powder compacts. The model combines crack tip toughness predicted by Kendall's model with crack tip shielding due to bridging of moisture meniscuses across the crack. The model predicts that crack tip shielding due to moisture should be dominant. Fracture tests on ceria green pellets verified that storing pellets at a high relative humidity (98% |
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"Instrumentation development for transient testing in tREAT" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85032926712 · ISSN: 0003-018X | |
"ATF-3: An overview of the accident tolerant fuels transient testing campaign in the TREAT reactor" [2015] Transactions of the American Nuclear Society · EID: 2-s2.0-84988864793 · ISSN: 0003-018X | |
"TREAT experiment vehicle design and future plans" [2015] Transactions of the American Nuclear Society · EID: 2-s2.0-84988894648 · ISSN: 0003-018X | |
"Mid-band corrosion in rover/NERVA fuels: An acoustic response to turbopump operation and their axial temperature profile" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84939125099 · ISSN: 0003-018X | |
"Submersion criticality safety of tungsten-rhenium urania cermet fuel for space propulsion and power applications" R.C. O’Brien, S.D. Howe, J.C. King, A.E. Craft, [2014] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2014.01.028 | |
"Durability evaluation of reversible solid oxide cells" James E. O'Brien, Robert C. O'Brien, Gregory K. Housley, Xiaoyu Zhang, [2013] Journal of Power Sources · DOI: 10.1016/j.jpowsour.2013.05.134 | |
"Improved durability of SOEC stacks for high temperature electrolysis" James E. O'Brien, Robert C. O'Brien, Joseph J. Hartvigsen, Greg Tao, Gregory K. Housley, Xiaoyu Zhang, [2013] International Journal of Hydrogen Energy · DOI: 10.1016/j.ijhydene.2012.09.176 | |
"Spark Plasma Sintering of W-UO2 cermets" N.D. Jerred, R.C. O’Brien, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.08.044 | |
"Spark Plasma Sintering of W-UO2 cermets" N.D. Jerred, R.C. O’Brien, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.08.044 · EID: 2-s2.0-84867753128 · ISSN: 0022-3115 | |
"LONG-TERM PERFORMANCE OF SOLID OXIDE STACKS WITH ELECTRODE-SUPPORTED CELLS OPERATING IN THE STEAM ELECTROLYSIS MODE" [2012] Proceedings of the Asme International Mechanical Engineering Congress and Exposition, 2011, Vol 4, Pts a and B | |
"Spark plasma sintering of fuel cermets for nuclear reactor applications"
Robert C. O’Brien, Steven D. Howe, Nathan D. Jerred, Kristopher Schwinn, Laura Sudderth, Joshua Hundley, Yang Zhong,
[2012]
Materials Research Society Symposium Proceedings
· DOI: 10.1557/opl.2012.416
· EID: 2-s2.0-84864879915
· ISSN: 0272-9172
The feasibility of the fabrication of tungsten based nuclear fuel cermets via Spark Plasma Sintering (SPS) is investigated in this work. CeO2 is used to simulate fuel loadings of UO2 or Mixed-Oxide (MOX) fuels within tungsten-based cermets due to the similar properties of these materials. This study shows that after a short time sintering, greater than 90 % density can be achieved, which is suitable to possess good strength as well as the ability to contain fission products. The mechanical properties and the densities of the samples are also investigated as functions of the applied pressures during the sintering. |
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"TESTING AND PERFORMANCE ANALYSIS OF NASA 5 CM BY 5 CM BI-SUPPORTED SOLID OXIDE ELECTROLYSIS CELLS OPERATED IN BOTH FUEL CELL AND STEAM ELECTROLYSIS MODES" [2012] Proceedings of the Asme International Mechanical Engineering Congress and Exposition, 2011, Vol 4, Pts a and B | |
"Mars reconnaissance lander: Vehicle and mission design" J.C. Bridges, R.M. Ambrosi, M.-C. Perkinson, J. Reed, L. Peacocke, N.P. Bannister, S.D. Howe, R.C. O'Brien, A.C. Klein, H.R. Williams, [2011] Planetary and Space Science · DOI: 10.1016/j.pss.2011.07.011 | |
"Mixed Americium-Curium Heat Sources for Radioisotope Heaters and Power Systems" J. A. Katalenich, R. C. O'Brien, [2011] Journal of Propulsion and Power · DOI: 10.2514/1.b34089 | |
"The Mars Hopper: an impulse driven, long range, long-lived mobile platform utilizing in-situ Martian resources" Robert C. O'Brien, Richard M. Ambrosi, Brian Gross, Jeff Katalenich, Logan Sailer, Mark McKay, John C. Bridges, Nigel P. Bannister, Steven D. Howe, [2011] Acta Astronautica · DOI: 10.1016/j.actaastro.2011.07.005 | |
"The Mars Hopper: an impulse-driven, long-range, long-lived mobile platform utilizing in situ Martian resources"
R C O'Brien, R M Ambrosi, B Gross, J Katalenich, L Sailer, J Webb, M McKay, J C Bridges, N P Bannister, S D Howe,
[2011]
Proceedings of the Institution of Mechanical Engineers Part G-Journal of Aerospace Engineering
· DOI: 10.1177/09544100jaero806
The requirements for performance by planetary exploration missions are increasing. Landing at a single location to take data is no longer sufficient. Due to the increasing cost, the missions that provide mobile platforms that can acquire data at displaced locations are becoming more attractive. Landers have also had limited range due to power limitations, limited lifetime of subsystems, and the inability to negotiate rough terrain. The Center for Space Nuclear Research has designed an instrumented platform that can acquire detailed data at hundreds of locations during its lifetime — a Mars Hopper. The Mars Hopper concept utilizes energy from radioisotopic decay in a manner different from any existing radioisotopic power source — as a thermal capacitor. By accumulating the heat from radioisotopic decay for long periods, though, the power of the source can be dramatically increased for short periods. Thus, a radioisotopic thermal rocket is possible. The platform will be able to ‘hop’ from one location to the next every 2—3 days with a separation of 10—20km per hop. Each platform will weigh around 50kg unfuelled which is the condition at deployment. Consequently, several platforms may be deployed on a single launch from Earth. With a lifetime estimated at 10 years, the entire surface of Mars can be mapped in detail by a couple dozen platforms. In addition, hoppers can collect samples and deliver them to the Mars Science Laboratory for more detailed analysis. Furthermore, the basic platform can be deployed to Europa, Titan, and even Venus with alterations — the propulsion system and operations essentially will be the same. |
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"Erratum to “Safe radioisotope thermoelectric generators and heat sources for space applications” [Journal of Nuclear Materials 377(2008) 506–521]" R.M. Ambrosi, N.P. Bannister, S.D. Howe, H.V. Atkinson, R.C. O’Brien, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.01.022 · ISSN: 0022-3115 | |
"Erratum to "Safe radioisotope thermoelectric generators and heat sources for space applications" [Journal of Nuclear Materials 377(2008) 506-521] (DOI:10.1016/j.jnucmat.2008.04.009)" R.M. Ambrosi, N.P. Bannister, S.D. Howe, H.V. Atkinson, R.C. O’Brien, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.01.022 · EID: 2-s2.0-64449088763 · ISSN: 0022-3115 | |
"Neutron sources for in-situ planetary science applications" R.M. Ambrosi, R.C. O’Brien, M.S. Skidmore, [2009] Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment · DOI: 10.1016/j.nima.2009.07.011 | |
"Spark Plasma Sintering of simulated radioisotope materials within tungsten cermets" R.M. Ambrosi, N.P. Bannister, S.D. Howe, H.V. Atkinson, R.C. O’Brien, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.05.012 | |
"Improving quantum efficiency and spectral resolution of a CCD through direct manipulation of the depletion region" Richard M. Ambrosi, Tony Abbey, Olivier Godet, R. O'Brien, M. J. L. Turner, Andrew Holland, Peter J. Pool, David Burt, David Vernon, Craig Brown, [2008] Proceedings of SPIE - The International Society for Optical Engineering · DOI: 10.1117/12.802622 · EID: 2-s2.0-70249097403 · ISSN: 0277-786X | |
"Safe radioisotope thermoelectric generators and heat sources for space applications" R.M. Ambrosi, N.P. Bannister, S.D. Howe, H.V. Atkinson, R.C. O’Brien, [2008] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2008.04.009 | |
Source: ORCID/CrossRef using DOI |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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