PNNL

Dr. Mychailo Toloczko is a materials scientist with more than 29 years of experience in structural alloys for many nuclear reactor systems. He is based in the Reactor Materials & Mechanical Design Group in the Energy and Environment Directorate at Pacific Northwest National Laboratory.

Current areas of active research include radiation effects on structural materials for advanced nuclear reactors and accelerators, and stress corrosion cracking of light water reactor (LWR) pressure boundary components and spent fuel dry cask storage systems. In the area of fast reactors and fusion energy devices, he spent 10 years studying creep of austenitic, tempered martensitic, and oxide dispersion strengthened iron-based alloys in neutron irradiation environments. His current focus for reactor core components is on measurement of tensile properties, fracture toughness, and microstructure of irradiated tempered martensitic steels to not only understand the limitations of existing alloys but also to develop improved alloys.

For light water applications, Dr. Toloczko leads research on precision stress corrosion crack (SCC) initiation and stress corrosion growth rate measurements of Ni-based alloys for pressurized water reactor (PWR) pressure boundary welds and reactor vessel feedthrough components. His programs provide data to both the U.S. Nuclear Regulatory Commission (NRC) and industry.

More recently, he has begun evaluating chloride-induced SCC behavior of stainless steels in support of lifetime estimates of spent fuel dry cask storage systems, supporting NRC and U.S. Department of Energy needs. All of his SCC test systems are built by staff at Pacific Northwest National Laboratory following his direction and are based on state-of-the-art methods that he has made more robust and able to evaluate a greater range of specimen types.

• PhD, materials sciences, Washington State University
• MS, nuclear engineering, University of California – Santa Barbara
• BA, physics, University of California – Berkeley

• Member of an Electric Power Research Institute (EPRI) expert panel to plan and discuss primary water SCC growth experiments on Alloy 690 and its weld metals.
• Working group member of the International Cooperative Group on Environmentally Assisted Cracking. This organization seeks to bring together scientists to research the topic of LWR stress corrosion cracking issues. It organizes a yearly meeting where recent research is presented and discussed. It also organizes collaborations between general members to help solve specific issues related to LWR SCC.
• Organization for Economic Co-operation and Development – Nuclear Energy Agency (OECD NEA) international expert group on innovative structural materials for nuclear reactors. This group seeks to integrate knowledge from several participating countries to better understand and recommend research activities in support of structural materials for a variety of reactor types, including fast reactors and LWRs.

U.S. Patent No. 8,679,458, March 25, 2014, "Functionalized Magnetic Nanoparticle Analyte Sensor"

Selected Publications Since 2000

2021

• Wang J., M.B. Toloczko, V. Voyevodin, V.V. Bryk, O.V. Borodin, V.V. Melnichenko, and A.S. Kalchenko, et al. 2021. "Atom Probe Tomography Characterization of High-Dose Ion Irradiated MA957." Journal of Nuclear Materials 545. PNNL-SA-151384. doi:10.1016/j.jnucmat.2020.152528
• Toloczko, M.B., Z. Zhai, R.A. Bouffioux, M.J. Olszta, S.M. Bruemmer, "Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Dissimilar Metal Interface Regions and Assessment of Program Results", NUREG/CR 7103, Vol. 5, 2021.
• Toloczko, M.B., Z. Zhai, J. Wang, M.J. Olszta, R.A. Bouffioux, "Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 2 (MRP-448), EPRI Document Number 3002018002, 2021.

2020

• Zhai Z., M.B. Toloczko, and S.M. Bruemmer, "Role of Material Condition in Precursor Corrosion Damage and Stress Corrosion Crack Initiation Behavior of Alloy 600 in PWR Primary Water." In CORROSION 2020, June 14-18, 2020, Online, NACE-2020-14536. Houston, Texas, NACE International, PNNL-SA-149432.

2019

• Olszta M.J., Z. Zhai, M.B. Toloczko, and S.M. Bruemmer. 2019. "Examination of Cavity Formation in Cold-Worked Alloy 690." In 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (EnvDeg 2019), August 18-22, 2019, Boston, MA, 274-285. La Grange Park, Illinois, American Nuclear Society, PNNL-SA-145060.
• Sainju R., C. Ophus, M.B. Toloczko, D.J. Edwards, and Y. Zhu. 2019. "Automated Quantitative Analysis of Extended Irradiation Defects - Dislocations, Voids and Precipitates in Neutron Irradiated HT-9 Steel." Microscopy and Microanalysis 25, no. S2:1564-1565. PNNL-SA-146581. doi:10.1017/S1431927619008559
• Wang J., D.K. Schreiber, N.A. Bailey, P. Hosemann, and M.B. Toloczko. 2019. "The Application of the OPTICS Algorithm to Cluster Analysis in Atom Probe Tomography Data." Microscopy and Microanalysis 25, no. 2:338-348. PNNL-SA-133361. doi:10.1017/S1431927618015386
• Zhai Z., M.B. Toloczko, and S.M. Bruemmer. 2019. "Effect of Material Condition on Stress Corrosion Crack Initiation of Cold-Worked Alloy 600 in Simulated PWR Primary Water." In 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (EnvDeg 2019), August 18-22, 2019, Boston, MA, 539-550. La Grange Park, Illinois, American Nuclear Society, PNNL-SA-143462.
• Zhai Z., M.J. Olszta, M.B. Toloczko, and S.M. Bruemmer. 2019. "Crack Initiation Behavior of Cold-Worked Alloy 690 in Simulated PWR Primary Water - Role of Starting Microstructure, Applied Stress and Cold Work on Precursor Damage Evolution." In 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (EnvDeg 2019), August 18-22, 2019, Boston, MA, 373-385. La Grange Park, Illinois, American Nuclear Society, PNNL-SA-145209.
• Zhu Y., G.W. Roberts, R. Sainju, B.J. Hutchinson, R.J. Kurtz, M.B. Toloczko, and D.J. Edwards, et al. 2019. "ADVANCED-STEM-BASED DEEP LEARNING FOR SEMANTIC SEGMENTATION OF DEFECTS IN STEELS." In Fusion Materials Semiannual Progress Report for the Period Ending December 31, 2018, edited by F.W. Wiffen and S. Melton. 83-84. DOE-ER-0313/65. Oak Ridge, Tennessee, Oak Ridge National Laboratory, PNNL-SA-141280.
• A Schemer-Kohrn, MB Toloczko, Y Zhu, J Wang, DJ Edwards, "Removal of FIB Damage using Flash Electropolishing for Artifact-free TEM Foils", Microscopy and Microanalysis 25 (S2), 1606-1607

2018

• Bruemmer S.M., M.J. Olszta, M.B. Toloczko, and D.K. Schreiber. 2018. "Grain Boundary Selective Oxidation and Intergranular Stress Corrosion Crack Growth of High-Purity Nickel Binary Alloys in High-Temperature Hydrogenated Water." Corrosion Science 131. PNNL-SA-129070. doi:10.1016/j.corsci.2017.11.024
• Toloczko M.B., Z. Zhai, and S.M. Bruemmer. 2018. "SCC Initiation Behavior of Alloy 182 in PWR Primary Water." In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (EDM 2017), edited by JH Jackson, D Paraventi and M Wright, 1, 137-160. Cham, Springer, PNNL-SA-128211. doi:10.1007/978-3-319-67244-1_9
• Zhai Z., M.B. Toloczko, and S.M. Bruemmer. 2018. "Microstructural Effects on SCC Initiation PWR Primary Water Cold-Worked Alloy 600." In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (EDM 2017), edited by JH Jackson, D Paraventi, M Wright, 1, 217-229. Cham, Springer. PNNL-SA-126736. doi:10.1007/978-3-319-67244-1_14
• Zhu Y., C. Ophus, M.B. Toloczko, and D.J. Edwards. 2018. "Towards bend-contour-free dislocation imaging via diffraction contrast STEM." Ultramicroscopy 193. PNNL-SA-131462. doi:10.1016/j.ultramic.2018.06.001

2017

• J Wang, MB Toloczko, K Kruska, DK Schreiber, DJ Edwards, Z Zhu, "Carbon Contamination During Ion Irradiation-Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels", Scientific reports 7 (1), 15813, 2017.
• Toloczko, M.B., "Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 1 (MRP-426), EPRI Document Number 3002010761, 2017.
• Shao L., J. Gigax, H. Kim, F. Garner, J. Wang, and M.B. Toloczko. 2017. "Carbon contamination, its consequences and its mitigation in ion-simulation of neutron-induced swelling of structural metals." In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 13-17, 2017, Portland, OR. The Minerals, Metals & Materials Series, edited by J.H. Jackson, D. Paraventi and M. Wright, 681-693. Cham:Springer. PNNL-SA-127786. doi:10.1007/978-3-030-04639-2_44
• Zhai Z., M.B. Toloczko, K. Kruska, and S.M. Bruemmer. 2017. "Precursor Evolution and Stress Corrosion Cracking Initiation of Cold-Worked Alloy 690 in Simulated Pressurized Water Reactor Primary Water." Corrosion 73, no. 10:1224-1236. PNNL-SA-125212. doi:10.5006/2470
• Zhai Z., M.B. Toloczko, K. Kruska, D.K. Schreiber, and S.M. Bruemmer. 2017. "Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water." In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (EDM 2017), edited by JH Jackson, D Paraventi and M Wright, 457-483. Cham, Springer, PNNL-SA-129136. doi:10.1007/978-3-319-67244-1_29
• Zhai Z., M.B. Toloczko, M.J. Olszta, and S.M. Bruemmer. 2017. "Stress Corrosion Crack Initiation of Alloy 600 in PWR Primary Water." Corrosion Science 123. PNNL-SA-123949. doi:10.1016/j.corsci.2017.04.013
• Bruemmer S.M., M.J. Olszta, R.J. Seffens, R.A. Bouffioux, N.R. Overman, M.B. Toloczko, "Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Behavior of Alloy 152 and 52 Welds", NUREG/CR 7103, Vol. 4, 2017.

2016

• Toloczko M.B., N.R. Overman, M.J. Olszta, S.M. Bruemmer, "Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys, Volume 3: Stress Corrosion Cracking of Cold Worked Alloy 690", NUREG/CR 7103, Vol. 3, 2016.
• Wang J., M.B. Toloczko, N.A. Bailey, F.A. Garner, J. Gigax, and L. Shao. 2016. "Modification of SRIM-Calculated Dose and Injected Ion Profiles Due to Sputtering, Injected Ion Buildup and Void Swelling." Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms 387. PNNL-SA-119227. doi:10.1016/j.nimb.2016.09.015
• JG Gigax, T Chen, H Kim, J Wang, LM Price, E Aydogan, SA Maloy,, "Radiation response of alloy T91 at damage levels up to 1000 peak dpa", Journal of Nuclear Materials 482, 2016, pp. 257-265.

2015

• Toloczko M.B., M.J. Olszta, N.R. Overman, and S.M. Bruemmer. 2015. "STRESS CORROSION CRACK GROWTH RESPONSE FOR ALLOY 152/52 DISSIMILAR METAL WELDS IN PWR PRIMARY WATER." In Proceedings of the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 11-15, 2016, Asheville, North Carolina. Houston, Texas:NACE International. PNNL-SA-97399.
• N.A. Bailey, E. Stergar, M. Toloczko, P. Hosemann, "Atom Probe Tomography Analysis of High Dose MA957 at Selected Irradiation Temperatures", Journal of Nuclear Materials, Vol. 459, 2015, pp. 225-234.

2014

• Baek J., T. Byun, S.A. Maloy, and M.B. Toloczko. 2014. "Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique." Journal of Nuclear Materials 444, no. 1-3:206-213. PNNL-SA-101694. doi:10.1016/j.jnucmat.2013.09.029
• Byun T., J. Baek, O. Anderoglu, S.A. Maloy, and M.B. Toloczko. 2014. "Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses." Journal of Nuclear Materials 449, no. 1-3:263-272. PNNL-SA-104176. doi:10.1016/j.jnucmat.2013.07.064
• Overman N.R., M.B. Toloczko, M.J. Olszta, and S.M. Bruemmer. 2014. "STRAIN CORRELATIONS IN ALLOY 690 MATERIALS USING ELECTRON BACKSCATTER DIFFRACTION AND VICKERS HARDNESS." In Corrosion 2014, March 9-13, 2014, San Antonio, Texas, Paper No. NACE-2014-4453. Houston, Texas:NACE International. PNNL-SA-99738.
• Toloczko M.B., F.A. Garner, V. Voyevodin, V.V. Bryk, O.V. Borodin, V.V. Melnichenko, and A.S. Kalchenko. 2014. "Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa." Journal of Nuclear Materials 453, no. 1-3:323-333. PNNL-SA-103933. doi:10.1016/j.jnucmat.2014.06.011

2013

• Anderoglu O., T. Byun, M.B. Toloczko, and S.A. Maloy. 2013. "Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors." Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science 44A, no. 1:70-83. PNNL-SA-94178. doi:10.1007/s11661-012-1565-y
• Byun T., M.B. Toloczko, T.A. Saleh, and S.A. Maloy. 2013. "Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF." Journal of Nuclear Materials 432, no. 1-3:1-8. PNNL-SA-96373. doi:10.1016/j.jnucmat.2012.07.019
• Stoller R.E., M.B. Toloczko, G.S. Was, A.G. Certain, S. Dwaraknath, and F.A. Garner. 2013. "On the Use of SRIM for Computing Radiation Damage Exposure." Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms 310. PNNL-SA-98405. doi:10.1016/j.nimb.2013.05.008
• Toloczko M.B., M.J. Olszta, N.R. Overman, and S.M. Bruemmer. 2013. "OBSERVATIONS AND IMPLICATIONS OF INTERGRANULAR STRESS CORROSION CRACK GROWTH OF ALLOY 152 WELD METALS IN SIMULATED PWR PRIMARY WATER." In Proceedings of the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 11-15, 2013, Asheville, North Carolina. Houston, Texas, NACE International, PNNL-SA-97397.
• M.B. Toloczko, M.J. Olszta, N.R. Overman, S.M. Bruemmer, "Stress Corrosion Crack Growth For Alloy 152/52 Dissimilar Metal Welds in PWR Primary Water", Proc. 16th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Asheville, NC, NACE International, 2013.
• S.M. Bruemmer, M.J. Olszta, N.R. Overman, M.B. Toloczko, "Microstructural Effects on Stress Corrosion Crack Growth in Cold-Worked Alloy 690 Tubing and Plate Materials", Proc. 16th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Asheville, NC, NACE International, 2013.
• N.R. Overman, M.B. Toloczko, M.J. Olszta, S.M. Bruemmer, "Strain Correlations in Alloy 690 Materials using Electron Back Scatter Diffraction and Vickers Hardness," Proceedings of Corrosion 2014, March 9-13, 2014, San Antonio, TX, NACE International.

2012

• Bruemmer S.M., M.B. Toloczko, and M.J. Olszta. 2012. Pacific Northwest National Laboratory Investigation of the Stress Corrosion Cracking in Nickel-Base Alloys, Volume 2. PNNL-20915; NUREG/CR-7103 Vol.2. Richland, WA: Pacific Northwest National Laboratory. Pacific Northwest National Laboratory Investigation of the Stress Corrosion Cracking in Nickel-Base Alloys, Volume 2
• Bruemmer S.M., M.J. Olszta, M.B. Toloczko, and L.E. Thomas. 2012. "Linking Grain Boundary Microstructure to Stress Corrosion Cracking of Cold Rolled Alloy 690 in PWR Primary Water." In CORROSION 2012 Conference & Expo, March 11-15, 2012, Salt Lake City, Utah, 7, 5912-5927. Houston, Texas, NACE International, PNNL-SA-85363.
• Byun T., W. Lewis, M.B. Toloczko, and S.A. Maloy. 2012. "Impact properties of irradiated HT9 from the fuel duct of FFTF." Journal of Nuclear Materials 421, no. 1 - 3:104 - 111. PNNL-SA-85024.
• Meyer R.M., P. Ramuhalli, M.B. Toloczko, L.J. Bond, and R.O. Montgomery. 2012. "Assessment of NDE Technologies for Detection and Characterization of Stress Corrosion Cracking in LWRs." In 3rd International Conference on NPP Life Management (PLIM) for Long Term Operations (LTO), May 14-18, 2012, Salt Lake City, Utah, Paper No. IAEA-CN--194-066A. Vienna, International Atomic Energy Agency, PNNL-SA-87826.
• Toloczko M.B., F.A. Garner, and S.A. Maloy. 2012. "Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF." Journal of Nuclear Materials 428, no. 1-3:170-175. PNNL-SA-84241. doi:10.1016/j.jnucmat.2012.04.005

2011

• Bruemmer S.M., M.B. Toloczko, "Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys, Volume 1", NUREG/CR 7103, Vol. 1, 2011.
• Maloy S.A., M.B. Toloczko, J.I. Cole, and T. Byun. 2011. "Core materials development for the fuel cycle R&D program." Journal of Nuclear Materials 415, no. 3:302-305. PNNL-SA-85136. doi:10.1016/j.jnucmat.2011.04.027
• Sundaram S.K., C.H. Henager, D.J. Edwards, A.L. Schemer-Kohrn, M. Bliss, B.J. Riley, and M.B. Toloczko, et al. 2011. "Hierarchical Microstructures in CZT." Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment 652, no. 1:174-177. PNNL-SA-73553. doi:10.1016/j.nima.2010.09.128
• Unwin S.D., P.P. Lowry, R.F. Layton, M.B. Toloczko, K.I. Johnson, and S.E. Sanborn. 2011. Physics-Based Stress Corrosion Cracking Component Reliability Model cast in an R7-Compatible Cumulative Damage Framework. PNNL-20596. Richland, WA: Pacific Northwest National Laboratory. Physics-Based Stress Corrosion Cracking Component Reliability Model cast in an R7-Compatible Cumulative Damage Framework
• Unwin S.D., P.P. Lowry, R.F. Layton, P.G. Heasler, and M.B. Toloczko. 2011. "Multi-State Physics Models of Aging Passive Components in Probabilistic Risk Assessment." In International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2011), March 13-17, 2011, Wilmington, North Carolina, 1, 161-172. La Grange Park, Illinois:Amercan Nuclear Society. PNNL-SA-76893.

2009

• Bruemmer S.M., M.B. Toloczko, M.J. Olszta, R.J. Seffens, and P.G. Efsing. 2009. "CHARACTERIZATION OF DEFECTS IN ALLOY 152, 52 AND 52M WELDS." In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, August 23-27, 2009, Virginia Beach, Virginia, 319-332. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-67526.
• Cumblidge S.E., S.R. Doctor, G.J. Schuster, R.V. Harris, S.L. Crawford, R.J. Seffens, and M.B. Toloczko, et al. 2009. "A Destructive Validation of NDE Responses of Service-Induced PWSCC Found in North Anna 2 Control Rod Drive Nozzle 31." In 7th International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurized Components. Tokyo:Japan Power Engineering and Inspection Corporation. PNNL-SA-66268.
• Toloczko M.B., and S.M. Bruemmer. 2009. "CRACK GROWTH RESPONSE OF ALLOY 152 AND 52 WELD METALS IN SIMULATED PWR PRIMARY WATER." In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, August 23-27, 2009, Virginia Beach, Virginia, 690-705. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-72538.
• Toloczko M.B., and S.M. Bruemmer. 2009. "CRACK GROWTH RESPONSE OF ALLOY 690 IN SIMULATED PWR PRIMARY WATER." In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, August 23-27, 2009, Virginia Beach, Virginia, 706-721. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-72539.

2008

• Allen T., J.T. Busby, R.L. Klueh, S.A. Maloy, and M.B. Toloczko. 2008. "Cladding and Duct Materials for Advanced Nuclear Recycle Reactors." JOM. The Journal of the Minerals, Metals and Materials Society 60, no. 1:15-23. PNNL-SA-57456. doi:10.1007/s11837-008-0002-6
• Bruemmer S.M., J.S. Vetrano, and M.B. Toloczko. 2008. "Microstructure and SCC Crack Growth of Nickel-Base Alloy 182 Weld Metal in Simulated PWR Primary Water." In Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 1658-1671. Toronto:Canadian Nuclear Society. PNWD-SA-7878.
• Cumblidge S.E., S.R. Doctor, G.J. Schuster, R. Harris, S.L. Crawford, R.J. Seffens, and M.B. Toloczko, et al. 2008. "NDE and DE of PWSCC Found in the J-Groove Weld of a Removed-From-Service Control Rod Drive Mechanism." In 6th International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurised Components, 723-733. Brussels:European Commission, Joint Research Centre. PNNL-SA-57354.
• Toloczko M.B., R.M. Ermi, D.S. Gelles, and R.J. Kurtz. 2008. "COMPRESSION TESTING OF V-4Cr-4Ti." In Fusion Materials Semiannual Report for the Period Ending June 30, 2008, edited by GR Nardella. 1-9. DOE/ER-0313/44. Oak Ridge, Tennessee:Oak Ridge National Laboratory. PNNL-SA-62165.
• Yantasee W., K. Hongsirikarn, C.L. Warner, D. Choi, T. Sangvanich, M.B. Toloczko, and M.G. Warner, et al. 2008. "Direct detection of Pb in urine and Cd, Pb, Cu, and Ag in natural waters using electrochemical sensors immobilized with DMSA functionalized magnetic nanoparticles." The Analyst 133, no. 3:348-355. PNNL-SA-57442. doi:10.1039/b711199a

2007

• Bliss M., D.C. Gerlach, J.B. Cliff, M.B. Toloczko, D.S. Barnett, G. Ciampi, and K.A. Jones, et al. 2007. "Pb Quantification of CdZnTe microheterogeneities complimented by SEM, IR microscopy, EDX, and TOF-SIMS." In Proceedings of the 11th Symposium on Radiation Measurements and Applications, published in Nuclear Instruments and Methods in Physics Research, Part A, 579, 138-140. Amsterdam:Elsevier. PNNL-SA-50517. doi:10.1016/j.nima.2007.04.018
• Cumblidge S.E., S.L. Crawford, S.R. Doctor, R.J. Seffens, G.J. Schuster, M.B. Toloczko, and R.V. Harris, et al. 2007. Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations. PNNL-16628. Richland, WA: Pacific Northwest National Laboratory. Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations
• Gelles D.S., M.B. Toloczko, and R.J. Kurtz. 2007. "Thermal Creep Mechanisms in V-4Cr-4Ti Pressurized Tube Specimens." Journal of Nuclear Materials 367-370, no. Pt. 1:869-875. PNNL-SA-53010. doi:10.1016/j.jnucmat.2007.03.067
• Toloczko M.B., P.L. Andresen, and S.M. Bruemmer. 2007. "SCC CRACK GROWTH OF COLD-WORKED TYPE 316 SS IN SIMULATED BWR OXIDIZING AND HYDROGEN WATER CHEMISTRY CONDITIONS." In Proceedings of the 13th International Conference on Environmental Degradation in Nuclear Power Systems, 1672-1683. Toronto:Canadian Nuclear Society. PNNL-SA-56486.

2006

• Gelles D.S., R.J. Kurtz, M.B. Toloczko, and L.E. Thomas. 2006. "FURTHER OBSERVATIONS ON V-4Cr-4Ti PRESSURIZED CREEP TUBES." In Fusion Materials Semiannual Report for the period ending December 31, 2005, DOE/ER-313/39. 2-10. Oak Ridge, Tennessee:Oak Ridge National Laboratory. PNNL-SA-48689.
• Maloy S.A., M.B. Toloczko, K.J. McClellan, T.J. Romero, Y. Kohno, F.A. Garner, and R.J. Kurtz, et al. 2006. "THE EFFECTS OF FAST REACTOR IRRADIATION CONDITIONS ON THE TENSILE PROPERTIES OF TWO FERRITIC/MARTENSITIC STEELS." Journal of Nuclear Materials 356, no. 1-3:62-69. PNNL-SA-53992.

2005

• S.A. Maloy, M.R. James, T.J. Romero, M.B. Toloczko, R.J. Kurtz, A. Kimura, "Tensile Properties of the NLF Reduced Activation Ferritic/Martensitic Steels after Irradiation in a Fast Reactor Spectrum to a Maximum Dose of 67 dpa", Journal of Nuclear Materials, Vol. 341, 2005, pp. 141-147.
• Maloy S.A., M.R. James, W.F. Sommer, G. Willcutt, M. Lopez, T.J. Romero, and M.B. Toloczko. 2005. "The Effect of 800 MeV Proton Irradiation on the Mechanical Properties of Tungsten at Room Temperature and at 475 Degrees C." Journal of Nuclear Materials 343, no. 1-3:219-226. PNNL-SA-47035.
• Simonen E.P., F.A. Garner, N.A. Klymyshyn, and M.B. Toloczko. 2005. "Response of PWR Baffle-Former Bolt Loading to Swelling, Irradiation Creep and Bolt Replacement as Revealed Using Finite Element Modeling." In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System - Water Reactors, edited by Todd R. Allen, Peter J. King and Lawrence Nelson, 449-459. Warrendale, Pennsylvania:The Minerals, Metals & Materials Society. PNNL-SA-46705.

2004

• M.B. Toloczko, D.S. Gelles, F.A. Garner, R.J. Kurtz, K. Abe, "Irradiation Creep and Swelling from 400 to 600°C of the Oxide Dispersion Strengthened Ferritic Alloy MA957", Journal of Nuclear Materials, Vols. 329-333, 2004, pp. 352-355.
• M.B. Toloczko, R.J. Kurtz, K. Abe, and A. Hasegawa, “Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture”, ASTM STP 1447, 2004, pp. 612-622.
• M.B. Toloczko and F.A. Garner, “Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling”, ASTM STP 1447, 2004, pp. 454-467.
• M.B. Toloczko, A.S. Kumar, M.L. Hamilton, S. Jumel, J.C Van Duysen, and L.L. Snead, “Effect of Copper Content on the Tensile Properties of Iron-Copper Alloys”, ASTM STP 1447, 2004, pp. 352-364.

2003

• S.A. Maloy, M.R. James, W.R. Johnson, T.S. Byun, K. Farrell, M.B. Toloczko, "Comparison of Fission Neutron and Proton/Spallation Neutron Effects on the Tensile Behavior of Type 316 and 304 Stainless Steel", Journal of Nuclear Materials, Vol. 318, 2003, pp. 283-291.
• Panetta P.D., M.B. Toloczko, F.A. Garner, and I.I. Balachov. 2003. Nondestructive Characterization of Aged Components. PNNL-14471. Richland, WA: Pacific Northwest National Laboratory. Nondestructive Characterization of Aged Components
• Toloczko M.B., M.L. Hamilton, and S.A. Maloy. 2003. "High Temperature Tensile Testing of Modified 9Cr-1Mo after Irradiation with High Energy Protons." Journal of Nuclear Materials 318, no. May 15, 2003:200-206. PNNL-SA-38035.

2002

• Toloczko M.B., R.J. Kurtz, A. Hasegawa, and K. Abe. 2002. "Shear Punch Tests Performed Using a New Low Compliance Test Fixture." Journal of Nuclear Materials 307, no. Pt B:1619-1623. PNNL-SA-37347.
• M.B. Toloczko, Y. Yokokura, K. Abe, M.L. Hamilton, F.A. Garner, and R.J. Kurtz, “Effect of Specimen Thickness on the Effective Shear Yield Strength and Effective Shear Ultimate Strength Obtained from the Shear Punch Test”, Small Specimen Test Techniques: 4th Volume, ASTM STP 1418, 2002, pp. 371-379.
• S. Nogami, S. Ohtsuka, M.B. Toloczko, A. Hasegawa, and K. Abe, “Analysis of Possible Deformation Mechanisms in SiC”, Journal of Nuclear Materials, Vols. 307-311, 2002, pp. 1178-1182.

2001

• M.B. Toloczko, K. Abe, M.L. Hamilton, F.A. Garner, and R.J. Kurtz, “The Effect of Test Machine Compliance on the Measured Shear Punch Yield Stress as Predicted Using Finite Element Analysis”, Materials Transactions, Japan Institute of Metals, Vol. 41, No. 10, 2001, pp. 1356-1359.

2000

• Toloczko M.B., J.P. Hirth, F.A. Garner, “Application of Generalized Deformation Theory to Irradiation Creep of FCC and BCC Stainless Steels”, J. of Nuclear Materials, Vols. 283-287, 2000, pp. 409-413.
• F.A. Garner, M.B. Toloczko, and B.H. Sencer, “Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure”, Journal of Nuclear Materials, Vol. 276, Issue: 1-3, January 1, 2000, pp. 123-142.
• M.B. Toloczko, M.L. Hamilton, and G.E. Lucas, “Ductility Correlations Between Shear Punch and Uniaxial Tensile Test Data”, J. of Nuclear Materials, Vols. 283-287, 2000, pp. 987-991.
• M.L. Hamilton and M.B. Toloczko, “Effect of Low Temperature Radiation in ATR on the Mechanical Properties of Ternary V-Cr-Ti Alloys as Determined by Tensile Tests and Shear Punch Tests”, J. of Nuclear Materials, Vols. 283-287, 2000, pp. 488-491.
• M.L. Hamilton, F.A. Garner, M.B. Toloczko, S.A. Maloy, W.F. Sommer, M.R. James, P.D. Ferguson, M.R. Louthan, Jr., “Shear Punch and Tensile Measurements of Mechanical Property Changes Induced in Various Steels by High Energy Mixed Proton and Neutron Irradiation at Low Temperatures”, J. of Nuclear Materials, Vols. 283-287, 2000, pp. 418-422.
• Garner F., M.B. Toloczko, L.R. Greenwood, C.R. Eiholzer, M.M. Paxton, and R.J. Puigh. 2000. "Swelling, irradiation creep and growth of pure rhenium irradiated with fast neutrons at 1030-1330 degrees C." Journal of Nuclear Materials 283-287, no. Part 1:380-385. PNNL-SA-31624.