Additive manufacturing for energy: A review C Sun, Y Wang, MD McMurtrey, ND Jerred, F Liou, J Li Applied Energy 282, 116041, 2021 | 265 | 2021 |
Spark plasma sintering of W–UO2 cermets RC O’brien, ND Jerred Journal of nuclear materials 433 (1-3), 50-54, 2013 | 56 | 2013 |
Deformation behavior and irradiation tolerance of 316 L stainless steel fabricated by direct energy deposition CH Shiau, MD McMurtrey, RC O'Brien, ND Jerred, RD Scott, J Lu, ... Materials & Design 204, 109644, 2021 | 23 | 2021 |
Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+ Sb as a mixed additive system to bind lanthanides MT Benson, Y Xie, JA King, KR Tolman, RD Mariani, I Charit, J Zhang, ... Journal of Nuclear Materials 510, 210-218, 2018 | 23 | 2018 |
Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility M McMurtrey, C Sun, RE Rupp, CH Shiau, R Hanbury, N Jerred, ... Journal of Nuclear Materials 545, 152739, 2021 | 21 | 2021 |
Capabilities development for transient testing of advanced nuclear fuels at TREAT NE Woolstenhulme, CC Baker, JD Bess, CB Davis, CM Hill, GK Housley, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 19 | 2016 |
Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel N Jerred, R Khanal, M Benson, E Perez, J King, M Dubey, J Burns, ... Scientific Reports 9 (16043), 1-14, 2019 | 17 | 2019 |
Pressure Resistance Welding of High Temperature Metallic Materials N Jerred, L Zirker, I Charit, J Cole, M Frary, D Butt, M Meyer, KL Murty Idaho National Lab.(INL), Idaho Falls, ID (United States), 2010 | 12 | 2010 |
Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels R Khanal, N Jerred, MT Benson, Y Xie, RD Mariani, I Charit, S Choudhury Journal of Nuclear Materials 540, 152372, 2020 | 10 | 2020 |
Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications ND Jerred, I Charit, LR Zirker, JI Cole Journal of Nuclear Materials 508, 265-277, 2018 | 10 | 2018 |
Nd, SbNd and Sb3Nd4 and their interactions with the cladding alloy HT9 ND Jerred, R Khanal, MT Benson, RD Mariani, S Choudhury, I Charit Journal of Nuclear Materials 541, 152387, 2020 | 9 | 2020 |
Dual-Mode propulsion system enabling Cubesat exploration of the solar system N Jerred, T Howe | 9 | 2018 |
A novel approach to selection of dopant to immobilize neodymium in uranium-based metallic fuels R Khanal, N Jerred, MT Benson, DA Andersson, RD Mariani, I Charit, ... Journal of Nuclear Materials 529, 151922, 2020 | 8 | 2020 |
Laser and pressure resistance weld of thin-wall cladding for LWR accident-tolerant fuels J Gan, N Jerred, E Perez, DC Haggard Jom 70, 192-197, 2018 | 7 | 2018 |
Spark plasma sintering of fuel cermets for nuclear reactor applications Y Zhong, RC O’Brien, SD Howe, ND Jerred, K Schwinn, L Sudderth, ... MRS Online Proceedings Library (OPL) 1383, mrsf11-1383-a01-08, 2012 | 7 | 2012 |
ODS Thin-wall Cladding Joining Technique Development J Gan, ND Jerred, EE Perez, BL Mackowiak, N Cordes, M Bachhav Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 5 | 2019 |
Status Report on Thin-Walled Cladding Weld Development and Test Fuel Cycle Research & Development Advanced Fuels Campaign J Gan, E Perez, DC Haggard, N Jerred INL/LTD-16-39760, 2016 | 5 | 2016 |
Diffusion study of uranium mononitride/zirconium carbide composite for space nuclear propulsion S Hamilton, ND Jerred, R Scott, M Bachhav, T Yao, VM Miller Journal of Nuclear Materials 583, 154535, 2023 | 4 | 2023 |
Laser Space Communication Concept for deep-space interplanetary missions using CubeSats A Rajguru, N Jerred, SD Howe, A Faler 45th AIAA Plasmadynamics and Lasers Conference, 2234, 2014 | 4 | 2014 |
The Mars Hopper: Development, Simulation and Experimental Validation of a Radioisotope Exploration Probe for the Martian Surface N Jerred, S Cooley, R O'Brien, S Howe, J O'Brien AIAA SPACE 2012 Conference & Exposition, 5152, 2012 | 4 | 2012 |