Mychailo B. Toloczko
Mychailo B. Toloczko
Pacific Northwest National Laborabory
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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: Beamá…, 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
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
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
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
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
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
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
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
Ductility correlations between shear punch and uniaxial tensile test data
MB Toloczko, ML Hamilton, GE Lucas
Journal of nuclear materials 283, 987-991, 2000
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
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
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
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
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 Environmentalá…, 2011
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
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
Irradiation creep and void swelling of two LMR heats of HT9 at {proportional_to} 400 C and 165 dpa
MB Toloczko, FA Garner
Irradiation creep and void swelling of two LMR heats of HT9 at∼ 400░ C and 165 dpa
MB Toloczko, FA Garner
Journal of nuclear materials 233, 289-292, 1996
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: Beamá…, 2017
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