| On the use of SRIM for computing radiation damage exposure RE Stoller, MB Toloczko, GS Was, AG Certain, S Dwaraknath, FA Garner Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2013 | 1536 | 2013 |
| Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure FA Garner, MB Toloczko, BH Sencer Journal of Nuclear Materials 276 (1-3), 123-142, 2000 | 657 | 2000 |
| Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at~ 400 C MB Toloczko, FA Garner, CR Eiholzer Journal of Nuclear Materials 212, 604-607, 1994 | 179 | 1994 |
| Direct detection of Pb in urine and Cd, Pb, Cu, and Ag in natural waters using electrochemical sensors immobilized with DMSA functionalized magnetic nanoparticles W Yantasee, K Hongsirikarn, CL Warner, D Choi, T Sangvanich, ... Analyst 133 (3), 348-355, 2008 | 135 | 2008 |
| Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500dpa MB Toloczko, FA Garner, VN Voyevodin, VV Bryk, OV Borodin, ... Journal of Nuclear Materials 453 (1), 323-333, 2014 | 124 | 2014 |
| Cladding and duct materials for advanced nuclear recycle reactors TR Allen, JT Busby, RL Klueh, SA Maloy, MB Toloczko JOM 60 (1), 15-23, 2008 | 108 | 2008 |
| Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors O Anderoglu, TS Byun, M Toloczko, SA Maloy Metallurgical and Materials Transactions A 44 (1), 70-83, 2013 | 98 | 2013 |
| Irradiation creep and swelling from 400 to 600 C of the oxide dispersion strengthened ferritic alloy MA957 MB Toloczko, DS Gelles, FA Garner, RJ Kurtz, K Abe Journal of nuclear materials 329, 352-355, 2004 | 94 | 2004 |
| Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems FA Garner, MB Toloczko Journal of nuclear materials 251, 252-261, 1997 | 93 | 1997 |
| Validation of the shear punch–tensile correlation technique using irradiated materials GL Hankin, MB Toloczko, ML Hamilton, RG Faulkner Journal of Nuclear Materials 258, 1651-1656, 1998 | 84 | 1998 |
| Ductility correlations between shear punch and uniaxial tensile test data MB Toloczko, ML Hamilton, GE Lucas Journal of nuclear materials 283, 987-991, 2000 | 83 | 2000 |
| Radiation response of alloy T91 at damage levels up to 1000 peak dpa JG Gigax, T Chen, H Kim, J Wang, LM Price, E Aydogan, SA Maloy, ... Journal of Nuclear Materials 482, 257-265, 2016 | 81 | 2016 |
| Linking grain boundary microstructure to stress corrosion cracking of cold-rolled alloy 690 in pressurized water reactor primary water SM Bruemmer, MJ Olszta, MB Toloczko, LE Thomas Corrosion 69 (10), 953-963, 2012 | 65 | 2012 |
| Shear punch tests performed using a new low compliance test fixture MB Toloczko, RJ Kurtz, A Hasegawa, K Abe Journal of nuclear materials 307, 1619-1623, 2002 | 62 | 2002 |
| Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water SM Bruemmer, MJ Olszta, MB Toloczko, DK Schreiber Corrosion Science 131, 310-323, 2018 | 59 | 2018 |
| Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials L Shao, J Gigax, D Chen, H Kim, FA Garner, J Wang, MB Toloczko Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2017 | 57 | 2017 |
| One dimensional cold rolling effects on stress corrosion crack growth in alloy 690 tubing and plate materials MB Toloczko, MJ Olszta, SM Bruemmer Proceedings of the 15th International Conference on Environmental …, 2011 | 57 | 2011 |
| Stress corrosion crack initiation of alloy 600 in PWR primary water Z Zhai, MB Toloczko, MJ Olszta, SM Bruemmer Corrosion Science, 2017 | 55 | 2017 |
| High temperature tensile testing of modified 9Cr–1Mo after irradiation with high energy protons MB Toloczko, ML Hamilton, SA Maloy Journal of nuclear materials 318, 200-206, 2003 | 53 | 2003 |
| Core materials development for the fuel cycle R&D program SA Maloy, M Toloczko, J Cole, TS Byun Journal of Nuclear Materials 415 (3), 302-305, 2011 | 52 | 2011 |
