| The Mars Hopper: An Impulse-Driven, Long-Range, Long-Lived Mobile Platform Utilizing In Situ Martian Resources SD Howe, RC O'Brien, RM Ambrosi, B Gross, J Katalenich, L Sailer, ... Proceedings of the Institution of Mechanical Engineers, Part G: Journal of …, 2011 | 35 | 2011 |
| A conceptual multi-megawatt system based on a tungsten cermet reactor JA Webb, B Gross Idaho National Lab.(INL), Idaho Falls, ID (United States), 2011 | 13 | 2011 |
| Conceptual design of a CERMET NTR fission core using multiphysics modeling techniques J Webb, B Gross, W Taitano 47th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit, 5947, 2011 | 9 | 2011 |
| A Combined Neutronic-Thermal Hydraulic Model of CERMET NTR Reactor JA Webb, B Gross, WT Taitano Idaho National Lab.(INL), Idaho Falls, ID (United States), 2011 | 9 | 2011 |
| Initial phase of Pu-238 production in Idaho National laboratory J Urban-Klaehn, D Miller, BJ Gross, CR Tyler, CC Dwight Applied Radiation and Isotopes 169, 109517, 2021 | 8 | 2021 |
| Recent 238Pu Production Activities at Idaho National Laboratory A Zillmer, W Green, C Tyler, B Gross, E Rosvall, A Fradeneck, J Fishler, ... Nuclear Technology 208 (sup1), S1-S10, 2022 | 3 | 2022 |
| Overview of recent Pu-238 production activities at idaho national laboratory AJ Zillmer, WS Green, CR Tyler, BJ Gross, ES Rosvall, AD Fradeneck, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 3 | 2021 |
| Overcoming challenges to support us resumption of high specific activity cobalt-60 RH Howard, MA Reichenberger, JM Urban-Klaehn, JL Peterson-Droogh, ... Applied Radiation and Isotopes 169, 109494, 2021 | 2 | 2021 |
| Data-driven methodology for predicting isotope production at material testing reactors J Navarro, J Peterson-Droogh, B Gross, RH Howard, W Cowherd, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 1 | 2019 |
| Coordinating Space Nuclear Research Advancement and Education JD Bess, JA Webb, BJ Gross, AE Craft Idaho National Lab.(INL), Idaho Falls, ID (United States), 2009 | 1 | 2009 |
| Determining the Oxidation Behavior of Matrix Graphite WEW Lu Cai, Rebecca E. Smith, Austin C. Matthews, David L. Cottle, William C ... Journal of Nuclear Materials, 2023 | | 2023 |
| Progress Report on Mockup Irradiation Capsule Fuel Measurements at LANSCE SC Vogel, JR Angell, DT Carver, AE Craft, CMW Fairbanks, BJ Gross, ... Los Alamos National Laboratory (LANL), Los Alamos, NM (United States), 2022 | | 2022 |
| Laboratory-Based 3D X-ray Imaging of Neutron-Irradiated Ceramic Particle Nuclear Fuel NL Cordes, BJ Gross, WC Chuirazzi, JJ Kane, JD Stempien Microscopy and Microanalysis 28 (S1), 2038-2039, 2022 | | 2022 |
| Typical Neutron Emission Spectra for Multi-Mission Radioisotope Thermoelectric Generator Fuel BJ Gross Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2022 | | 2022 |
| Commissioning of a Cask Enabling Characterization of Irradiated Nuclear Fuels with Pulsed Neutrons SC Vogel, JR Angell, DT Carver, AE Craft, CMW Fairbanks, BJ Gross, ... Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2021 | | 2021 |
| Neutronic Comparison of New HSA Cobalt Capsule Design to Legacy HSA Cobalt Capsule Design BJ Gross Idaho National Lab.(INL), Idaho Falls, ID (United States), 2018 | | 2018 |
| Fabrication and testing of a frozen pebble bed tungsten fuel element utilizing spark plasma sintering and the nuclear thermal rocket element environmental simulator BJ Gross 3rd Topical Meeting on Nuclear and Emerging Technologies for Space 2009 …, 2009 | | 2009 |
