ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ
ВАНТ. Серия: Ядерно-реакторные константы


Расширенное продолжение серии: Ядерные константы c 1971 года

Гарнер, Фрэнсис Альберт

Специалист в области радиационного материаловедения, четыре десятилетия занимавшийся исследованиями ядерных материалов в Хэнфорде (Westinghouse) и Тихоокеанской северо-западной национальной лаборатории, глава компании Radiation Effects Consulting, профессор-исследователь Техасского Университета и НИЯУ МИФИ. Автор и соавтор 473 научных работ, в том числе более 50 в 2013-2018 гг.

Представляемая специальность: 05.16.09 Материаловедение

ПУБЛИКАЦИИ 2013–2018 гг.

05.16 МЕТАЛЛУРГИЯ И МАТЕРИАЛОВЕДЕНИЕ
(05.16.09 Материаловедение (по отраслям)

  1. Corrigendum to “Accelerated materials evaluation for nuclear applications”.
    Griffiths M., Walters L., Greenwood L.R., Garner F.A.
    Journal of Nuclear Materials, 2017, vol. 488, pp. 46-62. doi: 10.1016/j.jnucmat.2017.09.014
  2. Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling.
    Gigax J.G., Kim H., Aydogan E., Garner F.A., Maloy S., Shao L.
    Materials Research Letters, 2017, vol. 5, no. 7, pp. 478-485. doi: 10.1080/21663831.2017.1323808
  3. Influence of injected interstitials on the void swelling in two structural variants of 304L stainless steel induced by self-ion irradiation at 500°C.
    Sun C., Garner F.A., Shao L., Zhang X., Maloy S.A.
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 2017, vol. 409, pp. 323-327. doi: 10.1016/j.nimb.2017.03.070
  4. Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials.
    Shao L., Gigax J., Chen D., Kim H., Garner F.A., Wang J., Toloczko M.B.
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 2017, vol. 409, pp. 251-254. doi: 10.1016/j.nimb.2017.05.026
  5. Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation.
    Chen T., Kim H., Gigax J.G., Chen D., Wei C.-C., Garner F.A., Shao L.
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 2017, vol. 409, pp. 259-263. doi: 10.1016/j.nimb.2017.05.024
  6. Corrigendum to “Accelerated materials evaluation for nuclear applications.”
    Griffiths M., Walters L., Greenwood L.R., Garner F.A.
    Journal of Nuclear Materials, 2017, vol. 492, pp. 292. doi: 10.1016/j.jnucmat.2017.05.002
  7. Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys.
    Aydogan E., Maloy S.A., Anderoglu O., Sun C., Gigax J.G., Shao L., Garner F.A., Anderson I.E., Lewandowski J.J.
    Acta Materialia, 2017, vol. 134, pp. 116-127. doi: 10.1016/j.actamat.2017.05.053
  8. Radiation instability of equal channel angular extruded T91 at ultra-high damage levels.
    Gigax J.G., Kim H., Chen T., Garner F.A., Shao L.
    Acta Materialia, 2017, vol. 132, pp. 395-404. doi: 10.1016/j.actamat.2017.04.038
  9. Accelerated materials evaluation for nuclear applications.
    Griffiths M., Walters L., Greenwood L.R., Garner F.A.
    Journal of Nuclear Materials, 2017, vol. 488, pp. 46-62. doi: 10.1016/j.jnucmat.2017.02.039
  10. Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions.
    Aydogan E., Chen T., Gigax J.G., Chen D., Wang X., Dzhumaev P.S., Emelyanova O.V., Ganchenkova M.G., Kalin B.A., Leontiva-Smirnova M., Valiev R.Z., Enikeev N.A., Abramova M.M., Wu Y., Lo W.Y., Yang Y., Short M., Maloy S.A., Garner F.A., Shao L.
    Journal of Nuclear Materials, 2017, vol. 487, pp. 96-104. doi: 10.1016/j.jnucmat.2017.02.006
  11. Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations.
    Aydogan E., Almirall N., Odette G.R., Maloy S.A., Anderoglu O., Shao L., Gigax J.G., Price L., Chen D., Chen T., Garner F.A., Wu Y., Wells P., Lewandowski J.J., Hoelzer D.T.
    Journal of Nuclear Materials, 2017, vol. 486, pp. 86-95. doi: 10.1016/j.jnucmat.2017.01.015
  12. BEAM-INDUCED TEMPERATURE CHANGES IN HVEM IRRADIATIONS.
    Garner F.A., Thomas L.E., Gelles D.S.
    Available at: https://www.scopus.com/inward/record.uri?eid=2-s2.0-0016868168&partnerID=40&md5=6e96d3660a8bd27cc917e7c58e769dd8, (2017).
  13. Radiation response of alloy T91 at damage levels up to 1000 peak dpa.
    Gigax J.G., Chen T., Kim H., Wang J., Price L.M., Aydogan E., Maloy S.A., Schreiber D.K., Toloczko M.B., Garner F.A., Shao L.
    Journal of Nuclear Materials, 2016, vol. 482, pp. 257-265. doi: 10.1016/j.jnucmat.2016.10.003
  14. Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling.
    Wang J., Toloczko M.B., Bailey N., Garner F.A., Gigax J., Shao L.
    Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 2016, vol. 387, pp. 20-28. doi: 10.1016/j.nimb.2016.09.015
  15. Monte Carlo modeling of cavity imaging in pure iron using back-scatter electron scanning microscopy.
    Yan Q., Gigax J., Chen D., Garner F.A., Shao L.
    Journal of Nuclear Materials, 2016, vol. 480, pp. 420-428. doi: 10.1016/j.jnucmat.2016.08.016
  16. Application of backscatter electrons for large area imaging of cavities produced by neutron irradiation.
    Pastukhov V.I., Аverin S.А., Panchenko V.L., Portnykh I.А., Freyer P.D., Giannuzzi L.A., Garner F.А.
    Journal of Nuclear Materials, 2016, vol. 480, pp. 289-300. doi: 10.1016/j.jnucmat.2016.07.059
  17. Simulated spatial and temporal dependence of chromium concentration in pure Fe and Fe–14%Cr under high dpa ion irradiation.
    Vörtler K., Mamivand M., Barnard L., Szlufarska I., Garner F.A., Morgan D.
    Journal of Nuclear Materials, 2016, vol. 479, pp. 23-35. doi: 10.1016/j.jnucmat.2016.06.040
  18. Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces.
    Chen T., Gigax J.G., Price L., Chen D., Ukai S., Aydogan E., Maloy S.A., Garner F.A., Shao L.
    Acta Materialia, 2016, vol. 116, pp. 29-42. doi: 10.1016/j.actamat.2016.05.042
  19. Blister formation on 13Cr2MoNbVB ferritic-martensitic steel exposed to hydrogen plasma.
    Nikitin A.V., Tolstolutskaya G.D., Ruzhytskyi V.V., Voyevodin V.N., Kopanets I.E., Karpov S.A., Vasilenko R.L., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 478, pp. 26-31. doi: 10.1016/j.jnucmat.2016.05.032
  20. Modeling injected interstitial effects on void swelling in self-ion irradiation experiments.
    Short M.P., Gaston D.R., Jin M., Shao L., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 471, pp. 200-207. doi: 10.1016/j.jnucmat.2015.10.002
  21. Analysis of structure and deformation behavior of AISI 316L tensile specimens from the second operational target module at the Spallation Neutron Source.
    Gussev M.N., McClintock D.A., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 210-220. doi: 10.1016/j.jnucmat.2015.07.013
  22. Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8-12% Cr ferritic-martensitic steels.
    Kupriiyanova Y.E., Bryk V.V., Borodin O.V., Kalchenko A.S., Voyevodin V.N., Tolstolutskaya G.D., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 264-273. doi: 10.1016/j.jnucmat.2015.07.012
  23. Influence of displacement damage on deuterium and helium retention in austenitic and ferritic-martensitic alloys considered for ADS service.
    Voyevodin V.N., Karpov S.A., Kopanets I.E., Ruzhytskyi V.V., Tolstolutskaya G.D., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 274-280. doi: 10.1016/j.jnucmat.2015.05.059
  24. Modeling injected interstitial effects on void swelling in self-ion experiments.
    Short M.P., Gaston D.R., Jin M., Shao L., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 471, pp. 200-207.
  25. Surface modification of low activation ferritic–martensitic steel EK-181 (Rusfer) by high temperature pulsed plasma flows.
    Emelyanova O.V., Dzhumaev P.S., Yakushin V.L., Kalin B.A., Ganchenkova M.G., Khein A.T., Leontyeva-Smirnova M.V., Valiev R.Z., Enikeev N.A., Shao L., Aydogan E., Short M., Garner F.
    Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 2015, vol. 365, pp. 218-221.
  26. Swelling of safety rod guide tubes in non-uniform fields of temperature and irradiation.
    Porollo S.I., Konobeev Yu.V., Garner F.A.
    Nuclear Energy and Technology, 2015, vol. 1, no. 2, pp. 88-92.
  27. Influence of displacement damage on deuterium and helium retention in austenitic and ferritic-martensitic alloys considered for ADS service.
    Voyevodin V.N., Karpov S.A., Kopanets I.E., Ruzhytskyi V.V., Tolstolutskaya G.D., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 274-280.
  28. Use of double and triple-ion irradiation to study the influence of helium and hydrogen on void swelling of 8-12% Cr ferritic-martensitic steels.
    Kupriiyanova Y.E., Bryk V.V., Borodin O.V., Kalchenko A.S., Voyevodin V.N., Tolstolutskaya G.D., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 264-273.
  29. Analysis of structure and deformation of AISI 316L tensile specimens from the second operational target module at the Spallation Neutron Source.
    Gussev M.N., McClintock D.A., Garner F.A.
    Journal of Nuclear Materials, 2016, vol. 468, pp. 210-220.
  30. Use of self-ion bombardment to study void swelling in advanced radiation-resistant alloys.
    Inhomogeneity of microstructure, mechanical properties, magnetism and corrosion observed in a 12Cr18Ni10Ti fuel assembly shroud irradiated in BN-350 to 59 dpa.

    Maksimkin O.P., Tsay K.V., Garner F.A.
    Journal of Nuclear Materials, 2015, vol. 467, pp. 899-910.
  31. Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates.
    Dong Y., Sencer B.H., Garner F.A., Marquis E.A.
    Journal of Nuclear Materials, 2015, vol. 467, pp. 692-702.
  32. Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation.
    Chen T., Aydogan E., Gigax J.G., Chen D., Wang J., Wang X., Ukai S., Garner F.A., Shao L.
    Journal of Nuclear Materials, 2015, vol. 467, pp. 42-49.
  33. Microstructural characterization and density change of 304 stainless steel reflector blocks after long-term irradiation in EBR-II.
    Huang Y., Wiezorek J.M.K., Garner F.A., Freyer P.D., Okita T., Sagisaka M., Isobe Y., Allen T.R.
    Journal of Nuclear Materials, 2015, vol. 465, pp. 516-530.
  34. The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450°C.
    Gigax J.G., Aydogan E., Chen T., Chen D., Shao L., Wu Y., Lo W.Y., Yang Y., Garner F.A.
    Journal of Nuclear Materials, 2015, vol. 465, pp. 343-348.
  35. Ion irradiation-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa.
    Toloczko M.B., Garner F.A., Voyevodin V.N., Bryk V.V., Borodin O.V., Mel'nychenko V.V., Kalchenko A.S.
    Journal of Nuclear Materials, 2014, vol. 453, pp. 323-333.
  36. Mechanical behavior of AISI 304SS determined by miniature test methods after neutron irradiation to 28 dpa.
    Rabenberg E.M., Jaques B.J., Sencer B.H., Garner F.A., Freyer P.D., Okita T., Butt D.P.
    Journal of Nuclear Materials, 2014, vol. 448, pp. 315-324.
  37. Using UT to assess neutron-induced damage.
    Isobe Y., Etoh J., Sagisaka M., Matsunaga T., Freyer P.D., Garner F.A., Okita T.
    Nuclear Engineering International, 2014, pp. 36-39.
  38. Validation of ultrasonic velocity measurements in first wall structural materials.
    Okita T., Etoh J., Sagisaka M., Matsunaga T., Isobe Y., Freyer P.D., Wiezorek J.M.K., Garner F.A.
    Fusion Science and Technology, 2014, vol. 66, pp. 77-82.
  39. Magnetic phase formation in irradiated austenitic alloys.
    Gussev M.N., Busby J.T., Tan L., Garner F.A.
    Journal of Nuclear Materials, 2014, vol. 448, pp. 294-300.
  40. Using UT to assess neutron-induced damage.
    Isobe Y., Etoh J., Sagisaka M., Matsunaga T., Freyer P.D., Garner F.A., Okita T.
    Nuclear Engineering International, 2014, pp. 36-39.
  41. On the use of SRIM for computing radiation damage exposure.
    Stoller R.E., Toloczko M.B., Was G.S., Certain A.G., Dwaraknath S., Garner F.A.
    Nuclear Instruments and Methods in Physics Research B, 2013, vol, 310, pp. 75-80.
  42. Development of a nondestructive inspection method for irradiation-induced microstructural evolution of thick 304 stainless steel blocks.
    Etoh J., Sagisaka M., Matsunaga T., Isobe Y., Garner F.A., Freyer P.D., Huang Y., Wiezorek J.M.K., Okita T.
    Journal of Nuclear Materials, 2013, vol. 440, pp. 500-507.
  43. Microstructure and swelling of neutron irradiated nickel and binary nickel alloys.
    Porollo S.I., Dvoraishin A.M., Konobeev Yu.V., Garner F.A.
    Journal of Nuclear Materials, 2013, vol. 442, pp. 809-812.
  44. Synergistic effects of helium and hydrogen on self-ion-induced swelling of austenitic 18Cr10NiTi stainless steel.
    Borodin O.V., Bryk V.V., Kalchenko A.S., Melnichenko V.V., Voyevodin V.N., Garner F.A.
    Journal of Nuclear Materials, 2013, vol. 442, pp. 817-820.
  45. Development of a nondestructive inspection method for irradiation-induced microstructural evolution of thick 304 stainless steel blocks.
    Etoh J., Sagisaka M., Matsunaga T., Isobe Y., Garner F.A., Freyer P.D., Huang Y., Wiezorek J.M.K., Okita T.
    Journal of Nuclear Materials, 2013, vol. 440, pp. 500-507.
  46. Microstructural defect evolution in neutron-irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing.
    Tsay K.V., Maksimkin O.P., Turubarova L.G., Rofman O.V., Garner F.A.
    Journal of Nuclear Materials, 2013, vol. 439, pp. 148-158.
  47. Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30-60 years.
    Kalchenko S., Bryk V.V., Lazarev N.P., Voyevodin V.N., Garner F.A.
    Journal of Nuclear Materials, 2013, vol. 437, pp. 415-423.