"Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen" Nathan Jerred, Mukesh Bachhav, Adrian R. Wagner, Tiankai Yao, Rabi Khanal, Samrat Choudhury, Indrajit Charit, James Zillinger, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155268 | |
"Resilience of uranium mononitride/zirconium carbide composites and uranium-zirconium carbonitride in hot hydrogen for nuclear thermal propulsion" James Zillinger, Randall Scott, Nathan Jerred, Kelsa Palomares, John Salasin, Victoria M. Miller, Sarah R. Hamilton, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155101 | |
"Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy" Rabi Khanal, Michael T. Benson, Samrat Choudhury, Indrajit Charit, Nathan D. Jerred, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.154966 | |
"Diffusion Study of Uranium Mononitride/Zirconium Carbide Composite for Space Nuclear Propulsion" Nathan D. Jerred, Randall Scott, Mukesh Bachhav, Tiankai Yao, Victoria M. Miller, Sarah Hamilton, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154535 | |
"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 | |
"Nd, SbNd and Sb3Nd4 and their interactions with the cladding alloy HT9" Rabi Khanal, Michael T. Benson, Robert D. Mariani, Samrat Choudhury, Indrajit Charit, Nathan D. Jerred, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152387 · ISSN: 0022-3115 | |
"Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels" Nathan Jerred, Michael T. Benson, Yi Xie, Robert D. Mariani, Indrajit Charit, Samrat Choudhury, Rabi Khanal, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152372 · ISSN: 0022-3115 | |
"Coupling of Spark Plasma Sintering with Advanced Modeling to Enable Process Scale-Up: Presentation to DOE-NE [Slides]" Troy Holland, Larry Aagesen Jr., Casey Icenhour, Derek Gaston, Albert Casagranda, Nathan Jerred, Daniel Schwen, Dennis Tucker, Stephanie Pitts, [2020] · DOI: 10.2172/2367279 | |
"A novel approach to selection of dopant to immobilize neodymium in uranium-based metallic fuels" Nathan Jerred, Michael T. Benson, David A. Andersson, Robert D. Mariani, Indrajit Charit, Samrat Choudhury, Rabi Khanal, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151922 · ISSN: 0022-3115 | |
"Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel"
Rabi Khanal, Michael T. Benson, Emmanuel Perez, James A. King, Megha Dubey, Jatuporn Burns, Indrajit Charit, Samrat Choudhury, Robert D. Mariani, Nathan D. Jerred,
[2019]
Scientific Reports
· DOI: 10.1038/s41598-019-51852-z
· ISSN: 2045-2322
Phase-stability in a U-Zr-Te-Nd multi-component metallic fuel for advanced nuclear reactors is systematically investigated by taking into account binary, ternary and quaternary interactions between elements involved. Historically, the onset of fuel-cladding chemical interactions (FCCI) greatly limits the burnup potential of U-Zr fuels primarily due to interactions between lanthanide fission products and cladding constituents. Tellurium (Te) is evaluated as a potential additive for U-Zr fuels to bind with lanthanide fission products, e.g. neodymium (Nd), negating or mitigating the FCCI effect. Potential fresh fuel alloy compositions with the Te additive, U-Zr-Te, are characterized. Te is found to completely bind with Zr within the U-Zr matrix. Alloys simulating the formation of the lanthanide element Nd within U-Zr-Te are also evaluated, where the Te-Nd binary interaction dominates and NdTe is found to form as a high temperature stable compound. The experimental observations agree well with the trends obtained from density functional theory calculations. According to the calculated enthalpy of mixing, Zr-Te compound formation is favored in the U-Zr-Te alloy whereas NdTe compound formation is favored in the U-Zr-Te-Nd alloy. Further, the calculated charge density distribution and density of states provide sound understanding of the mutual chemical interactions between elements and phase-stability within the multi-component fuel. |
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"Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications" I. Charit, L.R. Zirker, J.I. Cole, N.D. Jerred, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.05.046 | |
"Laser and Pressure Resistance Weld of Thin-Wall Cladding for LWR Accident-Tolerant Fuels" N. Jerred, E. Perez, D. C. Haggard, J. Gan, [2018] JOM · DOI: 10.1007/s11837-017-2697-8 · EID: 2-s2.0-85037143967 | |
"Capabilities development for transient testing of advanced nuclear fuels at TREAT" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019037883 | |
"Operations of a radioisotope-based propulsion system enabling cubesat exploration of the outer planets" [2014] 13th International Conference on Space Operations, SpaceOps 2014 · EID: 2-s2.0-84901273423 | |
"Development of the variable atmosphere testing facility for blow-down analysis of the mars hopper prototype" [2013] Nuclear and Emerging Technologies for Space, NETS 2013 · EID: 2-s2.0-84882800243 | |
"Spark Plasma Sintering of W-UO |
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"Current development of nuclear thermal propulsion technologies at the Center for Space Nuclear Research" [2012] AIAA SPACE Conference and Exposition 2012 · EID: 2-s2.0-84880987393 | |
"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
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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"The mars hopper: Development, simulation and experimental validation of a radioisotope exploration probe for the martian surface" [2012] AIAA SPACE Conference and Exposition 2012 · EID: 2-s2.0-84880995376 | |
"Development of a propulsion system and component test facility for advanced radioisotope powered Mars Hopper platforms" [2011] Nuclear and Emerging Technologies for Space 2011, NETS-2011 · EID: 2-s2.0-79960877310 | |
"First principles analysis of heat exchanger concepts and designs for a closed CO The overall scope of this article is to develop and investigate different heat exchanger concepts for a closed CO2 Brayton power cycle with regeneration that is part of the fission to surface power system (FSPS) concept from NASA, designed to function as a lunar outpost. The heat exchangers investigated are designed with the goal of utilizing ‘off the shelf technology’ and a sub-goal to ensure the heat exchangers designed are integrated into the FSPS as a whole. The FSP system utilizes two streams as the hot and cold sources: 850K sodium and potassium eutectic (NaK) stream from a nuclear reactor and 375K water stream cooled in titanium radiator piping as the cold source, which must be kept as a liquid. The thermodynamics and heat exchanger parameters were modelled and calculated using chemical process simulation software. The power delivered is 10kW electric per power conversion unit. There are three heat exchangers investigated as possible options for the NaK—CO2 hot side heat exchanger. When compared with a shell-and-tube heat exchanger, the compact heat exchangers are a better choice because they provide a lower mass system and a smaller footprint. |
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"The Mars Hopper: A radioisotope powered, impulse driven, long-range, long-lived mobile platform for exploration of Mars" [2011] Nuclear and Emerging Technologies for Space 2011, NETS-2011 · EID: 2-s2.0-79960879213 | |
"Pressure resistance welding of high temperature metallic materials" [2010] Materials Science and Technology Conference and Exhibition 2010, MS and T'10 · EID: 2-s2.0-79952647281 | |
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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