Materials Scientist
Materials Scientist

Patents

Publications

2025

  • Edwards D.J., A.L. Schemer-Kohrn, M.J. Olszta, R. Prabhakaran, Y. Zhu, J. Wang, and J.V. Haag, et al. 2025. "Understanding and Removing FIB Artifacts in Metallic TEM Samples Using Flash Electropolishing." Journal of Nuclear Materials 606:Art. No. 155618. PNNL-SA-202068. doi:10.1016/j.jnucmat.2025.155618
  • Toloczko M.B., R.A. Bouffioux, F. Cintron Colon, and Z. Zhai. 2025. Corrosion Fatigue Life Evaluation of 17-4PH in Support of Water Filled Turbine Hubs. PNNL-37335. Richland, WA: Pacific Northwest National Laboratory. Corrosion Fatigue Life Evaluation of 17-4PH in Support of Water Filled Turbine Hubs

2023

  • Guillen D., M.B. Toloczko, R. Prabhakaran, Y. Zhu, Y. Lu, and Y. Wu. 2023. "Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials." Materials 16, no. 16:Art. No. 5518. PNNL-SA-131070. doi:10.3390/ma16165518

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

2020

  • Zhai Z., M.B. Toloczko, and S.M. Bruemmer. 2020. "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), Sugust 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.

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 Wrigth, 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
  • Zhai Z., M.B. Toloczko, D.K. Schreiber, and S.M. Bruemmer. 2018. "Intergranular Stress Corrosion Crack Initiation and Temperature Dependence of Alloy 600 in Pressurized Water Reactor Primary Water." In Proceedings of CORROSION 2018 Conference & Expo, April 15-19, 2018, Phoenix, AZ, Paper No. NACE-2018-11522. Houston, Texas:NACE International. PNNL-SA-129755.
  • 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

  • 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
  • Shao L., J.G. Gigax, D. Chen, H. Kim, F. Garner, J. Wang, and M.B. Toloczko. 2017. "Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials." Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms 409. PNNL-SA-126514. doi:10.1016/j.nimb.2017.05.026
  • Wang J., M.B. Toloczko, K. Kruska, D.K. Schreiber, D.J. Edwards, Z. Zhu, and J. Zhang. 2017. "Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels." Scientific Reports 7, no. 1:Article No. 15813. PNNL-SA-129597. doi:10.1038/s41598-017-15669-y
  • Zhai Z., K. Kruska, M.B. Toloczko, and S.M. Bruemmer. 2017. "Precursor evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water." In CORROSION 2017, March 29-30, 2017, New Orleans, Louisiana, Paper No. NACE-2017-9475. Houston, Tx, Texas:NACE International. PNNL-SA-121146.
  • 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

2016

  • Gigax J., T. Chen, H. Kim, J. Wang, L. Price, E. Aydogan, and S.A. Maloy, et al. 2016. "Radiation Response of Alloy T91 at Damage Levels up to 1000 Peak DPA." Journal of Nuclear Materials 482. PNNL-SA-122928. doi:10.1016/j.jnucmat.2016.10.003
  • 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

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.

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 irradation 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
  • Olszta M.J., D.K. Schreiber, M.B. Toloczko, and S.M. Bruemmer. 2013. "ALLOY 690 SURFACE NANOSTRUCTURES DURING EXPOSURE TO PWR PRIMARY WATER AND POTENTIAL INFLUENCE ON STRESS CORROSION CRACKING INITIATION." In Proceedings of the 16th International Conference on Environmental Degradation of Nuclear Power Systems - Water Reactors, August 11-15, 2013, Asheville, NC, edited by P.L. Andresen, M.D. Wright and G.O. Ilevbare. Houston, Texas:NACE International. PNNL-SA-96869.
  • 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.

2012

  • 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

  • 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, 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:Amercian Nuclear Society. PNNL-SA-76893.

2010

  • Gelles D.S., M.B. Toloczko, and R.J. Kurtz. 2010. "A Search for Channel Deformation in Irradiated Vanadium Tensile Specimens." In Fusion Materials Semiannual Progress Report for the period ending December 31, 2009. DOE-ER-0313/47. Oak Ridge, Tennessee:Oak Ridge National Laboratory. PNNL-19199.

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

  • 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

  • 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

  • Toloczko M.B., and R.J. Kurtz. 2004. "ROOM TEMPERATURE COMPRESSION PROPERTIES OF TWO HEATS OF UNIRRADIATED V-4Cr-4Ti." In Fusion Materials: Semiannual Progress Report for Period Ending June 30, 2004, edited by R. L. Klueh and Teresa Roe. 13-18. Washington, District Of Columbia:DOE Office of Fusion Energy Sciences. PNNL-SA-42951. ROOM TEMPERATURE COMPRESSION PROPERTIES OF TWO HEATS OF UNIRRADIATED V-4Cr-4Ti
  • Toloczko M.B., D.S. Gelles, F.A. Garner, R.J. Kurtz, and K. Abe. 2004. "Irradiation Creep and Swelling from 400°C to 600°C of the Oxide Dispersion Strengthened Ferritic Alloy MA957." In Fusion Materials Semiannual Progress Report (DOE/ER-0313/35) for the period ending December 31, 2003.. 71-72. Springfield, Virginia:U.S. Department of Energy, Office of Fusion Energy. PNNL-SA-40891.

2003

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.

2000

  • 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.
  • Hamilton M.L., M.B. Toloczko, B.M. Oliver, and F.A. Garner. 2000. "Effect of Low Temperature Irradiation in ATR On The Mechanical Properties of Ternary V-Cr-Ti Alloys." In Fusion Materials: Semi-Annual Progress Report Ending December 31, 1999, edited by Rowcliffe, A.F. 76-95. Washington Dc:US Department of Energy, Office of Fusion Sciences. PNNL-SA-31871. Effect of Low Temperature Irradiation in ATR On The Mechanical Properties of Ternary V-Cr-Ti Alloys