본문 바로가기
KERD
논문KCI 등재

Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa

장창희|정채원|공병서|신지호|엄현준|Shao Lin
한국원자력학회 (Korean Nuclear Society)|2023.02|Nuclear Engineering and Technology|제55권 제2호|pp. 555-565|DOI 10.1016/j.net.2022.09.033

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

Austenitic stainless steelVoid swellingAdvanced radiation resistant alloyNanosized precipitatesNano indentationHeavy ion irradiation
주제분류원자력공학

초록

Despite many advantages as structural materials, austenitic stainless steels (SSs) have been avoided in many next generation nuclear systems due to poor void swelling resistance. In this paper, we report the results of heavy ion irradiation to the recently developed advanced radiation resistant austenitic SS (ARES-6P) with nanosized NbC precipitates. Heavy ion irradiation was performed at high temperatures (500 C and 575 C) to the damage level of ~200 displacement per atom (dpa). The measured void swelling of ARES-6P was 2e3%, which was considerably less compared to commercial 316 SS and comparable to ferritic martensitic steels. In addition, increment of hardness measured by nanoindentation was much smaller for ARES-6P compared to 316 SS. Though some nanosized NbC precipitates were dissociated under relatively high dose rate (~5.0 x 10-4 dpa/s), sufficient number of NbC precipitates remained to act as sink sites for the point defects, resulting in such superior radiation resistance

Abstract

Despite many advantages as structural materials, austenitic stainless steels (SSs) have been avoided in many next generation nuclear systems due to poor void swelling resistance. In this paper, we report the results of heavy ion irradiation to the recently developed advanced radiation resistant austenitic SS (ARES-6P) with nanosized NbC precipitates. Heavy ion irradiation was performed at high temperatures (500 C and 575 C) to the damage level of ~200 displacement per atom (dpa). The measured void swelling of ARES-6P was 2e3%, which was considerably less compared to commercial 316 SS and comparable to ferritic martensitic steels. In addition, increment of hardness measured by nanoindentation was much smaller for ARES-6P compared to 316 SS. Though some nanosized NbC precipitates were dissociated under relatively high dose rate (~5.0 x 10-4 dpa/s), sufficient number of NbC precipitates remained to act as sink sites for the point defects, resulting in such superior radiation resistance

참고문헌 (63)

  1. E. A. Kenik, "Radiation-induced degradation of stainless steel light water reactor internals", Mater. Sci. Eng. R Rep, 73(7), pp.67~83 (2012)
  2. S. J. Zinkle, "Structural materials for fission & fusion energy", Mater. Today, 12(11), pp.12~19 (2009)
  3. K. H. Lo, "Recent developments in stainless steels", Mater. Sci. Eng. R Rep, 65(4-6), pp.39~104 (2009)
  4. S. J. Zinkle, "Materials challenges in nuclear energy", Acta Mater, 61(3), pp.735~758 (2013)
  5. F. Garner, "Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors", Materials Science and Technology (2006)
  6. D. C. Crawford, "Fuels for sodium-cooled fast reactors : US perspective", J. Nucl. Mater, 371(1-3), pp.202~231 (2007)
  7. F. Garner, "Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic", martensitic alloys at high neutron exposure, 2000, pp.276(1-3), 123~142
  8. C. Sun, "Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments", Sci. Rep, 5(1), pp.1~7 (2015)
  9. G.S. Was, "Fundamentals of Radiation Materials Science: Metals and Alloys" (2016), springer
  10. P. Maziasz, "Temperature dependence of the dislocation microstructure of PCA austenitic stainless steel irradiated in ORR spectrally-tailored experiments", J. Nucl. Mater, 191, pp.701~705 (1992)
  11. R. Valiev, "Nanostructuring of metals by severe plastic deformation for advanced properties", Nat. Mater, 3(8), pp.511~516 (2004)
  12. E. Lee, "Fee15Nie13Cr austenitic stainless steels for fission and fusion reactor applications. III. Phase stability during heavy ion irradiation", J. Nucl. Mater, 278(1), pp.20~29 (2000)
  13. C. Solenthaler, "Precipitation strengthening of Nb-stabilized TP347 austenitic steel by a dispersion of secondary Nb(C,N) formed upon a short-term hardening heat treatment", Mater. Sci. Eng A, 647, pp.294~302 (2015)
  14. J. H. Shin, "Development of thermo-mechanical processing to form high density of uniformly distributed nanosized carbides in austenitic stainless steels", Mater. Sci. Eng A, 775, pp.138986~ (2020)
  15. N. Almousa, "On the use of non-destructive, gigahertz ultrasonics to rapidly screen irradiated steels for swelling resistance", Mater. Char, 174, pp.111017~ (2021)
  16. J. H. Shin, "Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation", J. Nucl. Mater, 564, pp.153678~ (2022)
  17. Y. W. Kim, "Effects of rolling temperature on the microstructure and mechanical properties of TieMo microalloyed hot-rolled high strength steel", Mater. Sci. Eng A, 605, pp.244~252 (2014)
  18. A. Deschamps, "Influence of predeformation on ageing in an AleZneMg alloydI. Microstructure evolution and mechanical properties", Acta Mater, 47(1), pp.281~292 (1998)
  19. H. Kim, "Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels", J. Nucl. Mater, 527, pp.151818~ (2019)
  20. J.G. Gigax, "The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 ℃", J. Nucl. Mater, 465, pp.343~348 (2015)
  21. R. E. Stoller, "On the use of SRIM for computing radiation damage exposure", Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. Atoms, 310, pp.75~80 (2013)
  22. T. Malis, "EELS log-ratio technique for specimenthickness measurement in the TEM", J. Electron. Microsc. Tech, 8(2), pp.193~200 (1988)
  23. Z. Fan, "From suppressed void growth to significant void swelling in NiCoFeCr complex concentrated solid-solution alloy", Materialia, 9, pp.100603~ (2020)
  24. P. Hosemann, "Issues to consider using nano indentation on shallow ion beam irradiated materials", J. Nucl. Mater, 425(1), pp.136~139 (2012)
  25. K. S. Mao, "Grain orientation dependence of nanoindentation and deformation-induced martensitic phase transformation in neutron irradiated AISI 304L stainless steel", Materialia, 5, pp.100208~ (2019)
  26. J. Gupta, "Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel:Heavy ions vs protons", J. Nucl. Mater, 501, pp.45~58 (2018)
  27. W. C. Oliver, "An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments", J. Mater. Res, 7(6), pp.1564~1583 (2011)
  28. W. D. Nix, "Indentation size effects in crystalline materials : a law for strain gradient plasticity", J. Mech. Phys. Solid, 46(3), pp.411~425 (1998)
  29. Z. Hu, "Effect of carbon on void swelling in Fe", 14th International Topical Meeting on Nuclear Applications of Accelerators, AccApp. (2021)
  30. Cavity Swelling in Irradiated Materials, "A. Bhattacharya", Oak Ridge National Lab.(ORNL), ~ (2020)
  31. L. Mansur, "Theory and experimental background on dimensional changes in irradiated alloys", J. Nucl. Mater, 216, pp.97~123 (1994)
  32. L. Mansur, "Correlation of neutron and heavy-ion damage: II. The predicted temperature shift if swelling with changes in radiation dose rate", J. Nucl. Mater, 78(1), pp.156~160 (1978)
  33. S.N. Votinov, "Irradiated Stainless Steels", pp.128~ (1987), Nauka publ.
  34. A. Kalchenko, "Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates", J. Nucl. Mater, 399(1), pp.114~121 (2010)
  35. A. Kalchenko, "Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30-60years", J. Nucl. Mater, 437(1-3), pp.415~423 (2013)
  36. J.-L. Seran, "Structural Materials for Generation IV Nuclear Reactors", pp.285~328 (2017), Elsevier
  37. P. Song, "Assessment of phase stability of oxide particles in different types of 15Cr-ODS ferritic steels under 6.4 MeV Fe ion irradiation at 200 ℃", J. Nucl. Mater, 529, pp.151953~ (2020)
  38. C. Lu, "Enhanced radiation-tolerant oxide dispersion strengthened steel and its microstructure evolution under helium-implantation and heavy-ion irradiation", Sci. Rep, 7(1), pp.1~7 (2017)
  39. N. Cautaerts, "Characterization of (Ti, Mo, Cr) C nanoprecipitates in an austenitic stainless steel on the atomic scale", Acta Mater, 164, pp.90~98 (2019)
  40. Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR-60 Reactor, "Y. Chen", Argonne National Lab.(ANL), ~ (2012)
  41. Swelling in Light Water Reactor Internal Components: Insights from Computational Modeling, "R. E. Stoller", Oak Ridge National Laboratory, ~, pp.ORNL (2015), LTR-2015[DOI]
  42. G. R. Odette, "On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science", Scripta Mater, 143, pp.142~148 (2018)
  43. Y. Yazawa, "Effect of matrix recrystallization on morphology, crystallography and coarsening behavior of vanadium carbide in austenite", Acta Mater, 52(12), pp.3727~3736 (2004)
  44. J. H. Shin, "Development of thermo-mechanical processing to form high density of uniformly distributed nanosized carbides in austenitic stainless steels", Mater. Sci. Eng A, 775, pp.138986~ (2020)
  45. E. A. Marquis, "Nuclear reactor materials at the atomic scale", Mater. Today, 12(11), pp.30~37 (2009)
  46. A. Hirata, "Atomic structure of nanoclusters in oxide-dispersion-strengthened steels", Nat. Mater, 10(12), pp.922~926 (2011)
  47. C. David, "A study of the effect of titanium on the void swelling behavior of D9 steels by ion beam simulation", J. Nucl. Mater, 383(1), pp.132~136 (2008)
  48. F. Abe, "Precipitate design for creep strengthening of 9% Cr tempered martensitic steel for ultra-supercritical power plants", Sci. Technol. Adv. Mater, 9(1), pp.013002~ (2008)
  49. B. Rouxel, "Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation", EPJ Nuclear Sci. Technol, 2 (2016)
  50. K. Nordlund, "Multiscale modelling of irradiation in nanostructures", J. Comput. Electron, 13(1), pp.122~141 (2014)
  51. R. Rajaraman, "A positron annihilation study of TiC precipitation in plastically deformed austenitic stainless steel", J. Nucl. Mater, 217(3), pp.325~328 (1994)
  52. M. Nastar, "Thermodynamic model for lattice point defect-mediated semi-coherent precipitation in alloys", Communications Materials, 2(1), pp.1~11 (2021)
  53. B. Rouxel, "Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation", EPJ Nuclear Sci. Technol, 2, pp.30~ (2016)
  54. P. Changizian, "Radiation effect on nanoindentation properties and deformation mechanisms of a Ni-based superalloy X-750", J. Nucl. Mater, 515, pp.1~13 (2019)
  55. J. Gan, "Microstructure evolution in austenitic FeeCreNi alloys irradiated with rotons : comparison with neutron-irradiated microstructures", J. Nucl. Mater, 297(2), pp.161~175 (2001)
  56. F. Kroupa, "Elastic interaction between prismatic dislocation loops and straight dislocations", Discuss. Faraday Soc, 38, pp.49~55 (1964)
  57. C. Sun, "Enhanced radiation tolerance of ultrafine grained FeeCreNi alloy", J. Nucl. Mater, 420(1-3), pp.235~240 (2012)
  58. J. H. Shin, "Dynamic evolution of nanosized NbC precipitates in austenite matrix during deformation and its contribution to strengthening", Mater. Sci. Eng A, 806, pp.140816~ (2021)
  59. J. T. Busby, "The relationship between hardness and yield stress in irradiated austenitic and ferritic steels", J. Nucl. Mater, 336(2-3), pp.267~278 (2005)
  60. A. Lupinacci, "Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction", J. Nucl. Mater, 458, pp.70~76 (2015)
  61. A. International, "Standard Test Method for Brinell Hardness of Metallic Materials", ASTM International, ~ (2012)
  62. F. Mompiou, "Sourcebased strengthening of sub-micrometer Al fibers", Acta Mater, 60(3), pp.977~983 (2012)
  63. B. Girault, "Strength effects in micropillars of a dispersion strengthened superalloy", Adv. Eng. Mater, 12(5), pp.385~388 (2010)

관련 논문AI추천

Swelling at high radiation damage levels of 120 and 240 dpa in 3.5 MeV self-ion irradiated ferritic/martensitic steels김건, 안상준, 이명규한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제10호X-Ray Diffraction line profile analysis of defects and precipitates in high displacement damage neutron-irradiated austenitic stainless steelsAshish K., Divakar R., Karthik V., Kumar Ran Vijay, Padmaprabu C., Sagdeo Archna, Shreevalli M.한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제1호The investigation of the carbon on irradiation hardening and defect clustering in RPV model alloy using ion irradiation and OKMC simulationLi Jianyang, Yang Yitao, Zhang Chonghong한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제6호Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features공병서, 곽동현, 심재민, 장윤석, 장창희한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제8호Effect of irradiation temperature on the nanoindentation behavior of P92 steel with thermomechanical treatmentHuang Xi, Li Guang, Li Qingshan, Li Xiaoyan, Li Zhenhe, Shen Yinzhong, Zhan Zixiong한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제7호양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향김동진, 임연수, 조성환, 최민재, 황성식한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2021 · 제20권 제3호

이 간행물의 다른 논문 (39건)

Separation and purification of elements from alkaline and carbonate nuclear waste solutionsSafiulina Alfiya M., Kostikova Galina V., Zhilov Valeriy I., Tsivadze Aslan Yu, Boyarintsev Alexander V., Stepanov Sergei I.pp. 391-407Beryllium oxide utilized in nuclear reactors: Part II: A systematic review of the neutron irradiation effectsZhou Xiang-wen, Hou Ming-dong, Liu Bingpp. 408-420Retrieval methodology for similar NPP LCO cases based on domain specific NLP성풍현, 이재희, 이종범, 성노규pp. 421-431Developing an interface strength technique using the laser shock methodSmith James A., Benefiel Bradley C., Scott Clark L.pp. 432-442TinyML Gamma Radiation ClassifierPietrosemoli Ermanno, Zennaro Marco, Altayeb Moezpp. 443-451
원문 보기