The Hollomon-Jaffe parameter is widely used in metallurgy and materials science to characterize the behavior and predict the various metals' physical-mechanical properties under different temperature and time modes. The possibility of predicting changes in the mechanical properties of structural steels due to thermal influences has been studied. The paper presents the results of a study of the mechanical properties of the materials of the core components of the BN-350 reactor facility (RF) made of austenite chromium-nickel steel 12Cr18Ni10Ti (a spent fuel assembly's jacket) and 09Cr16Ni15M3Nb (an intro-channel displacer). The samples were studied both before and after radiation annealing. Annealing of steel samples at 550 ℃ reduced the yield strength and significantly restored the plasticity and ability of the material to strain hardening. The efficiency of post-radiation annealing of the materials increases with annealing temperature and leads to a transition to the reduction process. It was established that medium of high temperature annealing during heat treatment does not lead to significant changes in the mechanical properties of irradiated materials. The microstructure studied using a scanning electron microscope reasonably correlates with the results of mechanical tests. The possibility of using the Hollomon-Jaffe parameter to predict the properties of austenite chromium-nickel steel, which received damaging doses in the range from 12 to 59 dpa, was shown for the first time. Thus, for the first time, the unique coefficient (C) of the Holloman-Jaffe parameter for irradiated materials of chromium-nickel steel was experimentally determined, and dependencies characterizing the change in hardness of chromium-nickel steel on temperature and duration of post-radiation thermal exposure were established.
Citation: Yerbolat Koyanbayev. Applying the Hollomon-Jaffe parameter to predict changes in mechanical properties of irradiated austenitic chromium-nickel steels during isothermal exposure[J]. AIMS Materials Science, 2024, 11(2): 216-230. doi: 10.3934/matersci.2024012
The Hollomon-Jaffe parameter is widely used in metallurgy and materials science to characterize the behavior and predict the various metals' physical-mechanical properties under different temperature and time modes. The possibility of predicting changes in the mechanical properties of structural steels due to thermal influences has been studied. The paper presents the results of a study of the mechanical properties of the materials of the core components of the BN-350 reactor facility (RF) made of austenite chromium-nickel steel 12Cr18Ni10Ti (a spent fuel assembly's jacket) and 09Cr16Ni15M3Nb (an intro-channel displacer). The samples were studied both before and after radiation annealing. Annealing of steel samples at 550 ℃ reduced the yield strength and significantly restored the plasticity and ability of the material to strain hardening. The efficiency of post-radiation annealing of the materials increases with annealing temperature and leads to a transition to the reduction process. It was established that medium of high temperature annealing during heat treatment does not lead to significant changes in the mechanical properties of irradiated materials. The microstructure studied using a scanning electron microscope reasonably correlates with the results of mechanical tests. The possibility of using the Hollomon-Jaffe parameter to predict the properties of austenite chromium-nickel steel, which received damaging doses in the range from 12 to 59 dpa, was shown for the first time. Thus, for the first time, the unique coefficient (C) of the Holloman-Jaffe parameter for irradiated materials of chromium-nickel steel was experimentally determined, and dependencies characterizing the change in hardness of chromium-nickel steel on temperature and duration of post-radiation thermal exposure were established.
[1] | Skakov MK, Melikhov VD (2001) Specific features of radiation inheritance. Russ Phys J 44: 608–612. https://doi.org/10.1023/A:1012543812065 doi: 10.1023/A:1012543812065 |
[2] | Xiao X (2019) Fundamental mechanisms for irradiation-hardening and embrittlement: A review. Metals 9: 1132. https://doi.org/10.3390/met9101132 doi: 10.3390/met9101132 |
[3] | Cole JI, Allen TR (2000) Microstructural changes induced by post-irradiation annealing of neutron-irradiated austenitic stainless steels. J Nucl Mater 283–287: 329–333. https://doi.org/10.1016/S0022-3115(00)00072-6 doi: 10.1016/S0022-3115(00)00072-6 |
[4] | Kascheev VA, Shadrin AYu, Dmitriev SA (2020) Optimization of RW volumes from reprocessing of SNF from fast reactors. Fractionation options. J Phys Conf Ser 1475: 012023. https://doi.org/10.1088/1742-6596/1475/1/012023 doi: 10.1088/1742-6596/1475/1/012023 |
[5] | Mitskevich AV (2015) Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA. Nucl Eng Technol 1: 202–207. https://doi.org/10.1016/j.nucet.2016.02.001 doi: 10.1016/j.nucet.2016.02.001 |
[6] | Podgornov VA (2014) Implementation of automated process control systems for SNF handling. NRNU MEPhI 11: 532–537. |
[7] | Dikov AS, Chernov II, Kislitsin SB (2018) Influence of the test temperature on the creep rate of 0.12C18Cr10NiTi structural steel irradiated in the BN-350 reactor. Inorg Mater Appl Res 9: 357–360. https://doi.org/10.1134/S2075113318030127 doi: 10.1134/S2075113318030127 |
[8] | Kuleshova EA, Fedotov IV, Maltsev DA, et al. (2022) Structural features ensuring the increase of service characteristics of high-nickel steels for pressure vessels of prospective energy-generation reactors. Int J Pres Ves Pip 200: 104845. https://doi.org/10.1016/j.ijpvp.2022.104845 doi: 10.1016/j.ijpvp.2022.104845 |
[9] | Bushuev AV, Kozhin AF, Glagovsky EM (2013) Determination of the residual content of fissile materials in fuel from spent fuel assemblies with high initial enrichment by the active neutron method. At Energy 114: 428–432. https://doi.org/10.1007/s10512-013-9734-7 doi: 10.1007/s10512-013-9734-7 |
[10] | Bushuev AV, Kozhin AF, Aleeva TB (2016) A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors. Phys At Nucl 79: 1362–1366. https://doi.org/10.1134/S1063778816080056 doi: 10.1134/S1063778816080056 |
[11] | Xu C, Chen WY, Zhang X, et al. (2018) Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel. J Nucl Mater 507: 188–197. https://doi.org/10.1016/j.jnucmat.2018.04.043 doi: 10.1016/j.jnucmat.2018.04.043 |
[12] | Sun Y, Obasi G, Hamelin C, et al. (2019) Characterisation and modelling of tempering during multi-pass welding. J Mater Process Technol 270: 118–131. https://doi.org/10.1016/j.jmatprotec.2019.02.015 doi: 10.1016/j.jmatprotec.2019.02.015 |
[13] | Virtanen E, Van Tyne CJ, Levy BS, et al. (2013) The tempering parameter for evaluating softening of hot and warm forging die steels. J Mater Process Technol 213: 1364–1369. https://doi.org/10.1016/j.jmatprotec.2013.03.003 doi: 10.1016/j.jmatprotec.2013.03.003 |
[14] | Liu G, Yang S, Han W, et al. (2018) Microstructural evolution of dissimilar welded joints between reduced-activation ferritic-martensitic steel and 316L stainless steel during the post weld heat treatment. Mater Sci Eng A 722: 182–196. https://doi.org/10.1016/j.msea.2018.03.035 doi: 10.1016/j.msea.2018.03.035 |
[15] | Cheng G, Choi KS, Hu X, et al. (2017) Predicting deformation limits of dual-phase steels under complex loading paths. JOM 69: 1046–1051. https://doi.org/10.1007/s11837-017-2333-7 doi: 10.1007/s11837-017-2333-7 |
[16] | Baklanov VV, Koyanbaev ET, Skakov MK, et al. (2017) Gripper for fastening of microsamples during tensile testing. Republic of Kazakhstan Patent No. 32305. |
[17] | Gordienko Yu, Ponkratov Yu, Kulsartov T, et al. (2020) Research facilities of IAE NNC RK (Kurchatov) for investigations of tritium interaction with structural materials of fusion reactors. Fusion Sci Technol 76: 703–709. https://doi.org/10.1080/15361055.2020.1777667 doi: 10.1080/15361055.2020.1777667 |
[18] | Batyrbekov E, Khasenov M, Gordienko Yu, et al. (2022) Experimental facility to study the threshold characteristics of laser action at the p-s-transition of noble gas atom upon excitation by 6Li(n, α)3H nuclear reaction products. Appl Sci 12: 12889. https://doi.org/10.3390/app122412889 doi: 10.3390/app122412889 |
[19] | Samarkhanov K, Batyrbekov E, Khasenov M, et al. (2019) Study of luminescence in noble gases and binary Kr-Xe mixture excited by the products of 6Li(n, α)T nuclear reaction. Eurasian Chem-Technol J 21: 115–123. https://doi.org/10.18321/ectj821 doi: 10.18321/ectj821 |
[20] | Gordienko Yu, Khasenov M, Batyrbekov E, et al. (2018) Luminescence of noble gases and their mixtures under nanosecond electron-beam excitation. J Appl Spectrosc 85: 600–604. https://doi.org/10.1007/s10812-018-0692-7 doi: 10.1007/s10812-018-0692-7 |
[21] | Koyanbayev YeT, Skakov MK, Batyrbekov EG, et al. (2019) The forecasting of corrosion damage of structural materials during dry long-term storage of RD BN-350 SNF with CC-19 SFA. Sci Technol Nucl Ins 2019: 1293060. https://doi.org/10.1155/2019/1293060 doi: 10.1155/2019/1293060 |
[22] | Rofman OV, Maksimkin OP, Koyanbayev YeT, et al. (2018) The natural aging of austenitic stainless steels irradiated with fast neutrons. J Nucl Mater 499: 284–293. https://doi.org/10.1016/j.jnucmat.2017.11.006 doi: 10.1016/j.jnucmat.2017.11.006 |
[23] | Koyanbayev ET, Sitnikov AA, Skakov MK, et al. (2017) Microstructural changes of mechanical properties of 08Cr18Ni10Ti austenitic steel under neutron irradiation. Key Eng Mater 743: 37–40. https://doi.org/10.4028/www.scientific.net/KEM.743.37 doi: 10.4028/www.scientific.net/KEM.743.37 |
[24] | Kozhakhmetov YeA, Koyanbayev YeT, Sapatayev Ye, et al. (2019) Study of the change in the physical and mechanical properties of materials of spent FAs of the BN-350 reactor under conditions of long-term thermal aging. NNC RK Bulletin 1: 45–51. https://doi.org/10.52676/1729-7885-2019-1-45-51 doi: 10.52676/1729-7885-2019-1-45-51 |
[25] | Koyanbayev YeT, Skakov MK, Ganovichev DA, et al. (2019) Simulation of the thermal conditions of cask with fuel assemblies of BN-350 reactor for dry storage. Sci Technol Nucl Ins 2019: 3045897. https://doi.org/10.1155/2019/3045897 doi: 10.1155/2019/3045897 |
[26] | Busby JT, Hash MC, Was GS (2005) The relationship between hardness and yield stress in irradiated austenitic and ferritic steels. J Nucl Mater 336: 267–278. https://doi.org/10.1016/j.jnucmat.2004.09.024 doi: 10.1016/j.jnucmat.2004.09.024 |
[27] | Larionov AS, Dikov АS, Poltavtseva VP, et al. (2015) Radiation thermal processes in Cr13Мo2NbVB steel—The material of the fuel assembly shell in reactor BN-350 under mechanical tests. IOP Conf Ser Mater Sci Eng 81: 012035. https://doi.org/10.1088/1757-899X/81/1/012035 doi: 10.1088/1757-899X/81/1/012035 |
[28] | Tsai KV, Maksimkin OP, Turubarova LG (2008) Influence of irradiation and post-radiation heat treatment on the microstructure and properties of 12C18N9T steel irradiated in the WWR-K research reactor up to 5 dpa. Probl At Sci Technol 92: 100–107. |
[29] | Garner FA (2012) Radiation damage in austenitic steels, In: Konings RJM, Comprehensive Nuclear Materials, 2 Eds., Oxford: Academic Press, 33–95. |
[30] | Lucas GE (1993) The evolution of mechanical property change in irradiated austenitic steels. J Nucl Mater 206: 287–305. https://doi.org/10.1016/0022-3115(93)90129-M doi: 10.1016/0022-3115(93)90129-M |
[31] | Nikolaeva AV, Nikolaev YA, Kevorkyan YR (2001) Restoration of mechanical properties of irradiated steel by thermal annealing. At Energy 90: 475–479. https://doi.org/10.1023/A:1012313210033 doi: 10.1023/A:1012313210033 |
[32] | Kryukov AM, Nikolaev YuA, Nikolaeva AV (1998) Behavior of mechanical properties of nickel-alloyed reactor pressure vessel steel under neutron irradiation and post-irradiation annealing. Nucl Eng Des 186: 353–359. https://doi.org/10.1016/S0029-5493(98)00247-7 doi: 10.1016/S0029-5493(98)00247-7 |
[33] | Tsai KV, Rofman OV, Ostavnov MA (2019) Change in the phase composition and strength properties of austenitic steel 12C18N10T as a result of deformation and post-deformation annealing. NNC RK Bulletin 1: 72–78. https://doi.org/10.52676/1729-7885-2019-1-72-78 doi: 10.52676/1729-7885-2019-1-72-78 |
[34] | Merezhko DA, Gussev MN, Merezhko MS, et al. (2022) Morphology and elemental composition of a new iron-rich ferrite phase in highly irradiated austenitic steel. Scripta Mater 215: 114690. https://doi.org/10.1016/j.scriptamat.2022.114690 doi: 10.1016/j.scriptamat.2022.114690 |
[35] | Amaev AD, Kryukov AM, Sokolov MA (1993) Recovery of transition temperature of irradiated WWER-440 vessel metal by annealing. ASTM STP 25: 369–379. https://doi.org/10.1520/STP24787S doi: 10.1520/STP24787S |
[36] | Merezhko MS, Merezhko DA, Rofman OV (2022) Macro-scale strain localization in highly irradiated stainless steel investigated using digital image correlation. Acta Mater 231: 117858. https://doi.org/10.1016/j.actamat.2022.117858 doi: 10.1016/j.actamat.2022.117858 |
[37] | Golovanov VN, Shamardin VK, Prokhorov VI, et al. (2001) Investigations of BOR-60 structural materials and prospects for further work. At Energy 91: 937–950. https://doi.org/10.1023/A:1014222025196 doi: 10.1023/A:1014222025196 |