Thermo-physical properties of DU–10 wt.% Mo alloys DE Burkes, CA Papesch, AP Maddison, T Hartmann, FJ Rice Journal of Nuclear Materials 403 (1-3), 160-166, 2010 | 96 | 2010 |
TAF-ID: An international thermodynamic database for nuclear fuels applications C Gueneau, N Dupin, L Kjellqvist, E Geiger, M Kurata, S Gosse, ... Calphad 72, 102212, 2021 | 72 | 2021 |
Thermal and transport properties of U3Si2 DJ Antonio, K Shrestha, JM Harp, CA Adkins, Y Zhang, J Carmack, ... Journal of Nuclear Materials 508, 154-158, 2018 | 51 | 2018 |
A study of constituent redistribution in U–Zr fuels using quantitative phase-field modeling and sensitivity analysis J Hirschhorn, MR Tonks, A Aitkaliyeva, C Adkins Journal of Nuclear Materials 523, 143-156, 2019 | 23 | 2019 |
Metallic fuels handbook DE Janney, CA Papesch, DE Burkes, JI Cole, RS Fielding, SM Frank, ... Idaho National Laboratory, 2017 | 22 | 2017 |
Phase characteristics of a number of U–Pu–Am–Np–Zr metallic alloys for use as fast reactor fuels DE Burkes, JR Kennedy, T Hartmann, CA Papesch, DD Keiser Jr Journal of nuclear materials 396 (1), 49-56, 2010 | 20 | 2010 |
Metallic Fuels Handbook, Part 1: Alloys Based on U-Zr, Pu-Zr, U-Pu, or U-Pu-Zr, Including Those with Minor Actinides (Np, Am, Cm), Rare-earth Elements (La, Ce, Pr, Nd, Gd), and … DE Janney, C Papesch Idaho National Lab.(INL), Idaho Falls, ID (United States), 2017 | 19 | 2017 |
Understanding fission gas bubble distribution, lanthanide transportation, and thermal conductivity degradation in neutron-irradiated α-U using machine learning L Cai, F Xu, FG Di Lemma, JJ Giglio, MT Benson, DJ Murray, CA Adkins, ... Materials Characterization 184, 111657, 2022 | 18 | 2022 |
A critical review of the experimentally known properties of U-Pu-Zr alloys. Part 1: phases and phase diagrams DE Janney, SL Hayes, CA Adkins Nuclear Technology, 2019 | 18 | 2019 |
TEM identification of subsurface phases in ternary U–Pu–Zr fuel A Aitkaliyeva, JW Madden, CA Papesch, JI Cole Journal of Nuclear Materials 473, 75-82, 2016 | 13 | 2016 |
Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm GL Beausoleil, C Petrie, W Williams, A Jokisaari, L Capriotti, S Novascone, ... Nuclear Technology 207 (10), 1491-1510, 2021 | 12 | 2021 |
The microstructure and thermodynamic behavior of as-cast U-24Pu-15Zr: Unexpected results and recommendations for U-Pu-Zr fuel research methodology J Hirschhorn, A Aitkaliyeva, C Adkins, M Tonks Journal of Nuclear Materials 518, 80-94, 2019 | 11 | 2019 |
TEM examination of phases formed between U–Pu–Zr fuel and Fe A Aitkaliyeva, JW Madden, BD Miller, CA Papesch, JI Cole Journal of Nuclear Materials 467, 717-723, 2015 | 10 | 2015 |
A critical review of the experimentally known properties of U-Pu-Zr alloys. Part 2: thermal and mechanical properties DE Janney, SL Hayes, CA Adkins Nuclear Technology 206 (1), 1-22, 2020 | 9 | 2020 |
FCRD Advanced Reactor (Transmutation) Fuels Handbook DE Janney, CA Papesch Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 9 | 2016 |
Fuel-cladding interaction between U-Pu-Zr fuel and Fe A Aitkaliyeva, JW Madden, BD Miller, CA Papesch, JI Cole Metallurgical and Materials Transactions E 2, 220-228, 2015 | 9 | 2015 |
FCRD Transmutation Fuels Handbook 2015 DE Janney, CA Papesch Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 9 | 2015 |
Atomic layer deposition of tungsten nitride films as protective barriers to hydrogen SK Bull, WW McNeary, CA Adkins, TA Champ, CA Hill, RC O'Brien, ... Applied Surface Science 507, 145019, 2020 | 8 | 2020 |
Demonstrate Thermal Property Measurement on Irradiated Fuel in IMCL CA Adkins, TR Pavlov, SC Middlemas, RS Schley, MC Marshall, MR Cole Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 7 | 2019 |
Microstructural characterization of the as-cast and annealed Pu-10Zr alloy A Aitkaliyeva, CA Adkins, J Hirschhorn, C McKinney, MR Tonks, ... Journal of Nuclear Materials 523, 80-90, 2019 | 7 | 2019 |