| Mechanical properties of irradiated UMo alloy fuel JL Schulthess, WR Lloyd, B Rabin, K Wheeler, TW Walters Journal of Nuclear Materials 515, 91-106, 2019 | 26 | 2019 |
| Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT J Schulthess, N Woolstenhulme, A Craft, J Kane, N Boulton, W Chuirazzi, ... Journal of Nuclear Materials 541, 152442, 2020 | 25 | 2020 |
| Effect of fission rate on the microstructure of coated UMo dispersion fuel A Leenaers, Y Parthoens, G Cornelis, V Kuzminov, E Koonen, ... Journal of Nuclear Materials 494, 10-19, 2017 | 15 | 2017 |
| Analysis of irradiated U-7wt% Mo dispersion fuel microstructures using automated image processing R Collette, J King, C Buesch, DD Keiser Jr, W Williams, BD Miller, ... Journal of Nuclear Materials 475, 94-104, 2016 | 14 | 2016 |
| Fission gas bubble identification using MATLAB's image processing toolbox R Collette, J King, D Keiser Jr, B Miller, J Madden, J Schulthess Materials Characterization 118, 284-293, 2016 | 13 | 2016 |
| Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions J Schulthess, D Kamerman, A Winston, A Pomo, T Trowbridge, X Pu, ... Journal of Nuclear Materials 560, 153520, 2022 | 12 | 2022 |
| Evaluation of gamma-ray transmission through rectangular collimator slits for application in nuclear fuel spectrometry L Senis, V Rathore, A Anastasiadis, EA Sundén, Z Elter, S Holcombe, ... Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2021 | 12 | 2021 |
| Thermal properties of U-Mo alloys irradiated under high fission power density DE Burkes, IJ Schwerdt, TK Huber, H Breitkreutz, C Reiter, W Petry, ... Journal of Nuclear Materials 547, 152823, 2021 | 11 | 2021 |
| Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes D Kamerman, F Cappia, K Wheeler, P Petersen, E Rosvall, T Dabney, ... Nuclear Materials and Energy 31, 101175, 2022 | 10 | 2022 |
| Elevated temperature tensile tests on DU–10Mo rolled foils J Schulthess, R Lloyd, B Rabin, M Heighes, T Trowbridge, E Perez Journal of Nuclear Materials 510, 282-296, 2018 | 10 | 2018 |
| Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding D Kamerman, N Woolstenhulme, D Imholte, A Fleming, C Jensen, ... Annals of Nuclear Energy 160, 108410, 2021 | 8 | 2021 |
| Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models BW Spencer, NE Woolstenhulme, JL Schulthess, AD Fleming, LA Astle, ... Journal of Nuclear Materials 568, 153816, 2022 | 7 | 2022 |
| TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project N Woolstenhulme, D Chapman, N Cordes, A Fleming, C Hill, C Jensen, ... Journal of Nuclear Materials 575, 154204, 2023 | 6 | 2023 |
| Benefits of utilizing CellProfiler as a characterization tool for U-10Mo nuclear Fuel R Collette, J Douglas, L Patterson, G Bahun, J King, D Keiser Jr., ... Materials Characterization 105 (2015), 71-81, 2015 | 5 | 2015 |
| Image fusion for neutron tomography of nuclear fuel W Chuirazzi, J Kane, A Craft, J Schulthess Journal of Radioanalytical and Nuclear Chemistry 331 (12), 5223-5229, 2022 | 4 | 2022 |
| Characterization Report for the MP-1 Experiment Fabrication Campaign R Kalsar, FG Di Lemma, T Trowbridge, E Tegtmeier, R Mccabe, ... Pacific Northwest National Laboratory (PNNL), Richland, WA (United States), 2020 | 4 | 2020 |
| A Comparative Study on Representativeness and Stochastic Efficacy of Miniature Tensile Specimen Testing S Karnati, SP Isanaka, Y Zhang, FF Liou, JL Schulthess Materials Performance and Characterization 11 (3), 424-439, 2022 | 3 | 2022 |
| Overview of the Water-Based RIA Testing in TREAT CP Folsom, JL Schulthess, DW Kamerman, NE Woolstenhulme, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 3 | 2021 |
| AGR-3/4 TRISO fuel compact ceramography JD Stempien, JL Schulthess Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 3 | 2020 |
| Measurement of kernel swelling and buffer densification in irradiated UCO and UO2 TRISO fuel particles from AGR-2 JD Stempien, MA Plummer, JL Schulthess, PA Demkowicz Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 3 | 2019 |
David KamermanIdaho National LaboratoryVerified email at inl.gov
