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Journal articles on the topic 'Irradiation creep'

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Author: Grafiati

Published: 10 December 2022

Last updated: 28 January 2023

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1

Liu, Ying, Wenbin Liu, Long Yu, Lirong Chen, Haonan Sui, and Huiling Duan. "Hardening and Creep of Ion Irradiated CLAM Steel by Nanoindentation." Crystals 10, no. 1 (January 17, 2020): 44. http://dx.doi.org/10.3390/cryst10010044.

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Ion irradiation, combined with nanoindentation, has long been recognized as an effective way to study effects of irradiation on the mechanical properties of metallic materials. In this research, hardening and creep of ion irradiated Chinese low activation martensitic (CLAM) steel are investigated by nanoindentation. Firstly, it is demonstrated that ion irradiation results in the increase of hardness, because irradiation-induced defects impede the glide of dislocations. Secondly, the unirradiated CLAM steel shows indentation creep size effect (ICSE) that the indentation creep strain decreases with the applied load, and ICSE is found to be associated with the variations of geometrical necessary dislocations (GNDs) density. However, ion irradiation results in the alleviation of ICSE due to the irradiation hardening. Thirdly, ion irradiation accelerates nanoindentation creep due to the large numbers of irradiation-induced vacancies whose diffusion controls creep deformation. Meanwhile, owing to the annihilation of vacancies, ion irradiation has a significant influence on the primary creep while only negligible influence has been observed for the steady-state creep.

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2

Zhu, Zhenbo, Hefei Huang, Jizhao Liu, Linfeng Ye, and Zhiyong Zhu. "Nanoindentation Study on the Creep Characteristics and Hardness of Ion-Irradiated Alloys." Materials 13, no. 14 (July 14, 2020): 3132. http://dx.doi.org/10.3390/ma13143132.

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The Hastelloy N alloy, Alloy 800H and 316H stainless steel were irradiated by Xe20+ ion irradiation with energy of 4 MeV at room temperature (peak damage ranging from 0.5 to 10 dpa). The micromechanical properties, hardness and creep plasticity, of these three investigated alloys were characterized before and after irradiation using nanoindentation. The results show that the hardness increases, and creep plasticity degrades with increasing ion dose in all the samples. In comparison, Hastelloy N has good irradiation damage resistance, while that of the 800H and 316H alloys is slightly worse. Additionally, the approximate positive relationship between irradiation hardening and creep plasticity degradation means that the property of creep plasticity of irradiated materials can be reflected from the nanohardness measurement for the heavy ion irradiation cases.

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3

Martin, J. L. "Creep and microstructure under irradiation." Radiation Effects 101, no. 1-4 (January 1987): 199–200. http://dx.doi.org/10.1080/00337578708224748.

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4

Matthews, J. R., and M. W. Finnis. "Irradiation creep models — an overview." Journal of Nuclear Materials 159 (October 1988): 257–85. http://dx.doi.org/10.1016/0022-3115(88)90097-9.

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5

Burchell, T. D., K. L. Murty, and J. Eapen. "Irradiation induced creep of graphite." JOM 62, no. 9 (September 2010): 93–99. http://dx.doi.org/10.1007/s11837-010-0145-0.

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6

Antipov, A. A., V. A. Gorokhov, V. V. Egunov, D. A. Kazakov, S. A. Kapustin, and Yu A. Churilov. "NUMERICAL SIMULATION OF HIGH-TEMPERATURE CREEP OF ELEMENTS OF HEAT-RESISTANT ALLOYS STRUCTURES TAKING INTO ACCOUNT NEUTRON IRRADIATION EFFECTS." Problems of strenght and plasticity 81, no. 3 (2019): 345–58. http://dx.doi.org/10.32326/1814-9146-2019-81-3-345-358.

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The technique of numerical research on the basis of FEM processes of deformation and damage accumulation in the structural elements of heat-resistant alloys under conditions of high-temperature creep taking into account the influence of neutron irradiation is developed. The description of the mechanical behavior of the material is carried out within the framework of the previously developed general model of the damaged material and the creep model for non-irradiated heat-resistant alloys, supplemented by taking into account the effect of irradiation on the creep rate and the appearance of brittle fracture in a given range of temperature variation and irradiation intensity. The defining relations of the creep model of the irradiated material were obtained by modifying the creep model of the non-irradiated material: a material function was introduced, taking into account the effect of the flux of neutrons on the rate of thermal creep deformation; a material function was introduced that takes into account the effect of the neutron flux on the creep surface radius; A material function was introduced, which takes into account the effect of the neutron flux on the ultimate value of the dissipation energy at full power. To simulate the processes of brittle fracture during creep under neutron irradiation conditions, it is assumed that the destructive values of effective normal stresses are a function of temperature, flux of neutrons and the current value of accumulated creep. The material functions of the model were obtained from the results of basic experiments conducted at the Research Institute of Mechanics for the heat-resistant alloy without irradiation under consideration and the available experimental data on the study of the creep of this alloy during its irradiation. Based on the proposed model, a numerical method for solving problems of high-temperature creep of structures made of heat-resistant alloys under neutron irradiation was developed and implemented within the UPAKS computing complex. To verify and illustrate the capabilities of the developed methodological and software tools, a number of problems of modeling the processes of high-temperature creep and destruction of structural elements made of the high-temperature alloy under consideration are solved.

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7

Gorokhov, V. A. "IDENTIFICATION AND VERIFICATION OF MATERIAL FUNCTIONS OF THE CREEP MODEL UNDER THERMAL RADIATION EFFECTS FOR AUSTENITIC STEEL 1X18H10T." Problems of strenght and plasticity 82, no. 1 (2020): 89–99. http://dx.doi.org/10.32326/1814-9146-2020-82-1-89-99.

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In the present paper, on the basis of the information available in the scientific literature on the thermal creep rate of 1X18H10T austenitic steel under neutron irradiation conditions, the material functions of the thermal creep model implemented and verified in the framework of the certified software for numerical modeling of structural deformation under thermal and thermal radiation effects of UPAKS software are obtained and verified. The list of identifiable material functions of the thermal creep model includes: a function that characterizes the initial creep strain rate, referred to a unit stress level at a given temperature level and stress parameter; the radius of the creep surface, which is a function of temperature; the hardening function, characterizing the change in the initial creep rate from the hardening parameter at a given temperature; a function that takes into account the effect of a fast neutron flux on the creep rate at a given temperature. Using an analytical approximation of experimental data describing the rate of thermal creep of steels under neutron irradiation depending on the stresses, temperature, and flux of fast neutrons, we obtained relations for determining the values of all the functions of the thermal creep model. The value of the radius of the creep surface for a fixed temperature was determined from the condition that the creep deformation for a selected period of time and the neutron flux accumulated during this time will not exceed 0.2%. Using the UPAKS software, the creep model and the obtained material functions implemented in them, numerical simulation of the deformation of 1X18H10T steel under conditions of prolonged thermal load and neutron irradiation was performed. The results of numerical modeling are in good agreement with the analytical dependences that describe the creep of a given material under uniaxial SSS. A numerical creep simulation was also carried out under the assumption of the absence of neutron irradiation. As in the case of neutron irradiation, good agreement is obtained between the calculated and experimental data.

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8

Karlsen, Wade, Mykola Ivanchenko, Ulla Ehrnsten, and Ken R. Anderson. "Post-Irradiation Examinations of Irradiation Creep Tested Zircaloy-2." Microscopy and Microanalysis 21, S3 (August 2015): 749–50. http://dx.doi.org/10.1017/s1431927615004547.

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9

Bystrov, L. N., L. I. Ivanov, and A. B. Tsepelev. "Irradiation-induced transient Creep of metals during pulsed irradiation." Radiation Effects 97, no. 1-2 (September 1986): 127–48. http://dx.doi.org/10.1080/00337578608208727.

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10

Pouchon, Manuel A., Jia Chao Chen, and W. Hoffelner. "Microcharacterization of Damage in Materials for Advanced Nuclear Fission Plants." Advanced Materials Research 59 (December 2008): 269–74. http://dx.doi.org/10.4028/www.scientific.net/amr.59.269.

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Miniature and sub-miniature samples were used for determination of mechanical properties of materials for advanced fission plants. Results from indentation and focused ion beam prepared micro-samples, punch tests and thin strip (irradiation) creep tests are shown. The results allow conclusions concerning materials damage. Irradiation damage profiles were determined with indentation. Results from micro-pillar tests showed a good agreement with results from conventional samples in case of oxide dispersion strengthened steels. Thin strip irradiation creep experiments revealed a negligible influence of dispersoid size/distribution on creep rates. Punch tests of fibre reinforced materials showed consistent results which still need quantitative analysis.

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11

Coghlan, W. A. "Review of recent irradiation creep results." International Materials Reviews 31, no. 1 (January 1986): 245–57. http://dx.doi.org/10.1179/imr.1986.31.1.245.

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12

Coghlan, W. A. "Review of recent irradiation creep results." International Metals Reviews 31, no. 1 (January 1986): 245–57. http://dx.doi.org/10.1179/imtr.1986.31.1.245.

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13

RUDEE, ENSIGN MERVYN LEA. "THE EFFECT OF IRRADIATION ON CREEP." Journal of the American Society for Naval Engineers 71, no. 3 (March 18, 2009): 453–56. http://dx.doi.org/10.1111/j.1559-3584.1959.tb01805.x.

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14

Tsai, H., H. Matsui, M. C. Billone, R. V. Strain, and D. L. Smith. "Irradiation creep of vanadium-base alloys." Journal of Nuclear Materials 258-263 (October 1998): 1471–75. http://dx.doi.org/10.1016/s0022-3115(98)00211-6.

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15

Fidleris, V. "The irradiation creep and growth phenomena." Journal of Nuclear Materials 159 (October 1988): 22–42. http://dx.doi.org/10.1016/0022-3115(88)90083-9.

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16

Garner, F. A., and D. S. Gelles. "Irradiation creep mechanisms: An experimental perspective." Journal of Nuclear Materials 159 (October 1988): 286–309. http://dx.doi.org/10.1016/0022-3115(88)90098-0.

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17

Ovsik, Martin, Michal Stanek, Martin Reznicek, and Lenka Hylova. "Study of Nano-Creep of Unfilled and Filled Cross-Linking Polypropylene." Materials Science Forum 919 (April 2018): 103–10. http://dx.doi.org/10.4028/www.scientific.net/msf.919.103.

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Cross-linking is a process in which polymer chains are associated through chemical bonds. Radiation, which penetrated through specimens and reacted with the cross-linking agent, gradually formed cross-linking (3D net), first in the surface layer and then in the total volume, which resulted in considerable changes in specimen behavior. This paper describes the effect of electron beam irradiation on the nanoindentation creep of unfilled and glass fiber filled polypropylene (25%). nanoindentation creep were measured by the DSI (Depth Sensing Indentation) method on samples which were non-irradiated and irradiated by different doses of the β – radiation (0, 30, 45 and 60 kGy). The purpose of the article is to consider to what extent the irradiation process influences the resulting nanoindentation creep measured by the DSI method. The unfilled and filled polypropylene tested showed significant changes of indentation creep. The measured results indicate, that electron beam irradiation is very effective tool for improvement of creep properties of unfilled and filled polypropylene. The nanoindentation creep after irradiated unfilled Polypropylene was decreased up to 16 % (filled polypropylene was decreased up to 9%) compared to non-irradiated surface. These changes were examined and confirmed by Gel content.

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18

Breslavsky, Dmitry, Aleksandr Chuprynin, Oleg Morachkovsky, Oksana Tatarinova, and Will Pro. "Deformation and damage of nuclear power station fuel elements under cyclic loading." Journal of Strain Analysis for Engineering Design 54, no. 5-6 (July 2019): 348–59. http://dx.doi.org/10.1177/0309324719874923.

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Deformation and damage of nuclear power station fuel element shells under irradiation and cyclic loading due vibrations are studied. Constitutive equations include dependencies for a creep-damage equation with a scalar damage parameter, as well as terms for thermal and irradiation creep strains, elastic, thermal, and swelling strains. The acceleration of the creep-damage process due to cyclic variation of internal pressure is considered with a dynamic creep model, for which constitutive equations are derived using the method of asymptotic expansions and averaging over a period of cyclic loading. Stress and strain states in the fuel element shell are determined by use of an in-house finite element method creep-damage code for shells of revolution. Results show the essential variation in the initially symmetric fuel element shell form, as well as the acceleration of creep-damage processes due to the cyclic pressure.

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19

MURAKAMI, Sumio, and Mamoru MIZUNO. "Elaboration of constitutive equations of creep and creep damaga under irradiation." Journal of the Society of Materials Science, Japan 40, no. 449 (1991): 158–64. http://dx.doi.org/10.2472/jsms.40.158.

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20

Yu, Qianran, Giacomo Po, and Jaime Marian. "Physics-based model of irradiation creep for ferritic materials under fusion energy operation conditions." Journal of Applied Physics 132, no. 22 (December 14, 2022): 225101. http://dx.doi.org/10.1063/5.0101561.

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Irradiation creep is known to be an important process for structural materials in nuclear environments, potentially leading to creep failure at temperatures where thermal creep is generally negligible. While there is a great deal of data for irradiation creep in steels and zirconium alloys in light water reactor conditions, much less is known for first wall materials under fusion energy conditions. Lacking suitable fusion neutron sources for detailed experimentation, modeling, and simulation can help bridge the dose-rate and spectral-effects gap and produce quantifiable expectations for creep deformation of first wall materials under standard fusion conditions. In this paper, we develop a comprehensive model for irradiation creep created from merging a crystal plasticity representation of the dislocation microstructure and a defect evolution simulator that accounts for the entire cluster dimensionality space. Both approaches are linked by way of a climb velocity that captures dislocation-biased defect absorption and a dislocation strengthening term that reflects the accumulation of defect clusters in the system. We carry out our study in Fe under first wall fusion reactor conditions, characterized by a fusion neutron spectrum with average recoil energies of 20 keV and a damage dose rate of [Formula: see text] dpa/s at temperatures between 300 and 800 K.

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21

Robertson, C., M. H. Mathon, B. K. Panigrahi, S. Amirthapandian, S. Sojak, and S. Santra. "Indentation response of model oxide dispersion strengthening alloys after ion irradiation up to 700 °C." Journal of Applied Physics 132, no. 17 (November 7, 2022): 175107. http://dx.doi.org/10.1063/5.0092138.

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This paper presents an experimental investigation of irradiation-induced evolutions in three different oxide dispersion strengthening (ODS) alloys. High-dose, dual beam Ni–He ion irradiations are carried out up to 700 °C. The significant dose-dependent changes in the ODS particle size and number density are documented and interpreted in terms of specific point defect transport mechanisms, from small angle neutron scattering, TEM, and pulsed low-energy positron system measurements combined. The corresponding micro-mechanical changes in the alloys are evaluated based on the indentation response, which is, in turn, interpreted in terms of related, sub-grain plasticity mechanisms. The room temperature tests (without dwell time) reveal that the microscale work-hardening rate increases with decreasing the particle number density and pronounced strain localization effect. The elevated temperature tests (up to 600 °C, with dwell time) show that the indentation creep compliance is mostly temperature-independent after irradiation up to 25 dpa at Tirr = 500 °C and markedly temperature-dependent, after irradiation beyond 40 dpa at Tirr = 600 °C. This effect is ascribed to particular creep mechanisms associated with indent-induced plasticity, i.e., high stress and high dislocation density conditions.

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22

Tai, Kaiping, Robert S. Averback, Pascal Bellon, and Yinon Ashkenazy. "Irradiation-induced creep in nanostructured Cu alloys." Scripta Materialia 65, no. 2 (July 2011): 163–66. http://dx.doi.org/10.1016/j.scriptamat.2011.04.001.

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23

Shankar, Vani, and Gary S. Was. "Proton irradiation creep of beta-silicon carbide." Journal of Nuclear Materials 418, no. 1-3 (November 2011): 198–206. http://dx.doi.org/10.1016/j.jnucmat.2011.06.047.

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24

Erasmus, Christiaan, Schalk Kok, and Michael P. Hindley. "Significance of primary irradiation creep in graphite." Journal of Nuclear Materials 436, no. 1-3 (May 2013): 167–74. http://dx.doi.org/10.1016/j.jnucmat.2012.11.007.

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25

Xu, Cheng, and Gary S. Was. "Proton irradiation creep of FM steel T91." Journal of Nuclear Materials 459 (April 2015): 183–93. http://dx.doi.org/10.1016/j.jnucmat.2015.01.023.

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26

Jung, Peter. "Irradiation creep of 20% cold-worked copper." Journal of Nuclear Materials 200, no. 1 (March 1993): 138–40. http://dx.doi.org/10.1016/0022-3115(93)90017-s.

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27

Schüle, Wolfgang, and Hermann Hausen. "Neutron irradiation creep in stainless steel alloys." Journal of Nuclear Materials 212-215 (September 1994): 388–92. http://dx.doi.org/10.1016/0022-3115(94)90091-4.

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28

Nagakawa, Johsei, H. Shiraishi, M. Okada, H. Kamitsubo, I. Kohno, and T. Shikata. "Irradiation creep simulation at low proton flux." Journal of Nuclear Materials 133-134 (August 1985): 497–500. http://dx.doi.org/10.1016/0022-3115(85)90197-7.

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29

Scholz, R., and G. E. Youngblood. "Irradiation creep of advanced silicon carbide fibers." Journal of Nuclear Materials 283-287 (December 2000): 372–75. http://dx.doi.org/10.1016/s0022-3115(00)00264-6.

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30

Nagakawa, Johsei, N. Yamamoto, and H. Shiraishi. "Computer simulation of early-stage irradiation creep." Journal of Nuclear Materials 179-181 (March 1991): 986–89. http://dx.doi.org/10.1016/0022-3115(91)90256-7.

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31

MURAKAMI, Sumio, Mamoru MIZUNO, and Toshiaki OKAMOTO. "A constitutive equation of irradiation creep and swelling under neutron irradiation." Journal of the Society of Materials Science, Japan 39, no. 445 (1990): 1353–59. http://dx.doi.org/10.2472/jsms.39.1353.

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32

Dai, Dongliang, and Meiwu Shi. "Effects of electron beam irradiation on structure and properties of ultra-high molecular weight polyethylene fiber." Journal of Industrial Textiles 47, no. 6 (January 29, 2017): 1357–77. http://dx.doi.org/10.1177/1528083717690612.

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This study introduced trimethylolpropane trimethacrylate into ultra-high molecular weight polyethylene fibers through supercritical CO2 pretreatment before the fibers were irradiated under an electron beam. Significant differences, emerging in the ultra-high molecular weight polyethylene fibers’ gel content, mechanical properties, and creep property according to their different irradiation doses, were studied through one-way analysis of variance. Regression equations were established between the irradiation dose and the gel content, breaking strength, elongation at break, and creep rate by regression analysis. A reasonable irradiation dosage range was determined after a verification experiment and the impact trends were analyzed; additionally, the sensitized irradiation crosslinking mechanism of ultra-high molecular weight polyethylene fibers was preliminarily examined. Then the surface morphology, chemical structures, thermal properties, and crystal properties of treated ultra-high molecular weight polyethylene fibers were measured. The results showed that as the irradiation dose increased, the gel content first rose and then declined; the breaking strength decreased continuously; the elongation at break increased at first and then decreased; and the creep rate originally fell and then rose before finally declining slowly. Electron beam irradiation had a significant etching effect on the fibers’ surface, and both the melting point and crystallinity decreased slightly.

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33

Konovalov, Igor I., Boris A. Tarasov, and Eduard M. Glagovskiy. "Irradiation Creep of Uranium-Plutonium Nitride Fuel and Serviceability of Fuel Element." Defect and Diffusion Forum 375 (May 2017): 91–100. http://dx.doi.org/10.4028/www.scientific.net/ddf.375.91.

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Article discusses experimental data on creep of (U,Pu)N and other uranium compounds, and possible mechanism of mass-transfer. Proposed equation describes the following creep features: weak temperature dependence at T < 1000°C, creep acceleration in a fuel with micron-sized grains, and acceleration with the content of second phases formed by impurities and fission products. The difference in creep behavior in reactors with thermal and fast neutrons environmentsis discussed. Comparison of irradiation creep of nitride fuel and properties of cladding materials shows that under parameters of fast reactors and typical design of fuel element it is impossible to implement restraining of external nitride swelling. As initial porosity in the fuel will not compensate the nitride swelling, the cladding of fuel element will work in a mode of following the changing of fuel size. Some suggestions on the cladding material properties are done.

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34

Griffiths, Malcolm. "Effect of Neutron Irradiation on the Mechanical Properties, Swelling and Creep of Austenitic Stainless Steels." Materials 14, no. 10 (May 17, 2021): 2622. http://dx.doi.org/10.3390/ma14102622.

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Austenitic stainless steels are used for core internal structures in sodium-cooled fast reactors (SFRs) and light-water reactors (LWRs) because of their high strength and retained toughness after irradiation (up to 80 dpa in LWRs), unlike ferritic steels that are embrittled at low doses (<1 dpa). For fast reactors, operating temperatures vary from 400 to 550 °C for the internal structures and up to 650 °C for the fuel cladding. The internal structures of the LWRs operate at temperatures between approximately 270 and 320 °C although some parts can be hotter (more than 400 °C) because of localised nuclear heating. The ongoing operability relies on being able to understand and predict how the mechanical properties and dimensional stability change over extended periods of operation. Test reactor irradiations and power reactor operating experience over more than 50 years has resulted in the accumulation of a large amount of data from which one can assess the effects of irradiation on the properties of austenitic stainless steels. The effect of irradiation on the intrinsic mechanical properties (strength, ductility, toughness, etc.) and dimensional stability derived from in- and out-reactor (post-irradiation) measurements and tests will be described and discussed. The main observations will be assessed using radiation damage and gas production models. Rate theory models will be used to show how the microstructural changes during irradiation affect mechanical properties and dimensional stability.

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35

Lin, Han, Li Min Dong, Chen Wang, Tong Xiang Liang, and Jie Mo Tian. "Structure and Properties of Irradiation Crosslinked UHMWPE." Key Engineering Materials 602-603 (March 2014): 656–60. http://dx.doi.org/10.4028/www.scientific.net/kem.602-603.656.

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Irradiation crosslinking is one of the most important methods to modify UHMWPE, it can effectively improve the hardness, creep resistance and abrasion resistance of this material. In order to eliminate free radical, increase material strength, abrasion resistance and fatigue resistance of creep, this study uses Co60-γ to modify UHMWPE under vacuum atmosphere, with the irradiation dose of 30, 60, 90, 120 Kgy respectively. Its mechanical properties, microstructure, degree of crosslinking and crystallinity are analyzed, the results show that the modified UHMWPEs impact strength decreased, elongation basically remain unchanged, tensile fracture strength and tensile yield strength increased.

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36

Luborsky, F. E., R. H. Arendt, R. L. Fleischer, H. R. Hart, J. E. Tkaczyk, and D. A. Orsini. "Effect of internal fission-fragment irradiation on critical currents and flux creep in Bi–Sr–Ca–Cu–O superconductors doped with UO2." Journal of Materials Research 8, no. 6 (June 1993): 1277–84. http://dx.doi.org/10.1557/jmr.1993.1277.

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Fission fragment damage was introduced into samples of Bi2Sr2CaCu2Ox and Bi1.7Pb0.3Sr2Ca2Cu3Oy, doped with various levels of UO2, by irradiation with thermal neutrons. The critical temperatures were unchanged. Concurrent with an increase in intragranular Jc previously reported, a decrease in flux creep was observed. The apparent pinning potential for creep at 10 K and 0.8 T increased on irradiation by about two to three times for both the 2212 and 2223 compounds. This increased apparent pinning potential is attributed to the strong pinning introduced by the damage caused by the travel of the fission fragments through the crystal. Pinning potential after irradiation increased with an increase in the amount of UO2 in the sample. The increase in bulk pinning potential on irradiation was proportional to the increase in intragranular critical currents on irradiation, qualitatively as expected theoretically.

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37

Garud, Yogendra S. "Low temperature creep and irradiation creep in nuclear reactor applications: A critical review." International Journal of Pressure Vessels and Piping 139-140 (March 2016): 137–45. http://dx.doi.org/10.1016/j.ijpvp.2016.02.002.

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38

Didenko, T. P., and P. О. Selyshchev. "Features of the Transient Creep under an Irradiation." METALLOFIZIKA I NOVEISHIE TEKHNOLOGII 38, no. 2 (April 19, 2016): 175–87. http://dx.doi.org/10.15407/mfint.38.02.0175.

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39

Scholz, R., and R. Matera. "Irradiation creep induced stress relaxation of Inconel 718." Fusion Engineering and Design 51-52 (November 2000): 165–70. http://dx.doi.org/10.1016/s0920-3796(00)00313-6.

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40

Woo, C. H. "Irradiation creep and growth under cascade damage conditions." Philosophical Magazine A 70, no. 4 (October 1994): 713–24. http://dx.doi.org/10.1080/01418619408242257.

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41

Hall, M. M. "Irradiation creep relaxation of void swelling-driven stresses." Journal of Nuclear Materials 432, no. 1-3 (January 2013): 166–74. http://dx.doi.org/10.1016/j.jnucmat.2012.08.015.

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42

Sarkar, Apu, Jacob Eapen, Anant Raj, K. L. Murty, and T. D. Burchell. "Modeling irradiation creep of graphite using rate theory." Journal of Nuclear Materials 473 (May 2016): 197–205. http://dx.doi.org/10.1016/j.jnucmat.2016.01.036.

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43

Borodin, V. A. "SIPA-induced correlation between irradiation creep and swelling." Journal of Nuclear Materials 206, no. 1 (November 1993): 97–100. http://dx.doi.org/10.1016/0022-3115(93)90239-u.

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44

Borodin, V. A. "The effect of swelling on SIPA irradiation creep." Journal of Nuclear Materials 225 (August 1995): 15–21. http://dx.doi.org/10.1016/0022-3115(94)00440-4.

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45

Gilbert, E. R., B. A. Chin, and D. R. Duncan. "Effect of irradiation on failure mode during creep." Metallurgical Transactions A 18, no. 1 (January 1987): 79–84. http://dx.doi.org/10.1007/bf02646224.

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46

Jawaharram, Gowtham Sriram, Christopher M. Barr, Anthony M. Monterrosa, Khalid Hattar, Robert S. Averback, and Shen J. Dillon. "Irradiation induced creep in nanocrystalline high entropy alloys." Acta Materialia 182 (January 2020): 68–76. http://dx.doi.org/10.1016/j.actamat.2019.10.022.

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47

Shann, S. H., and L. F. Van Swam. "Creep anisotropy of Zircaloy-2 cladding during irradiation." Nuclear Engineering and Design 148, no. 1 (June 1994): 17–25. http://dx.doi.org/10.1016/0029-5493(94)90238-0.

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Davies, Mark A., and Mark Bradford. "A revised description of graphite irradiation induced creep." Journal of Nuclear Materials 381, no. 1-2 (October 2008): 39–45. http://dx.doi.org/10.1016/j.jnucmat.2008.07.019.

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Burchell, Timothy D. "Irradiation induced creep behavior of H-451 graphite." Journal of Nuclear Materials 381, no. 1-2 (October 2008): 46–54. http://dx.doi.org/10.1016/j.jnucmat.2008.07.022.

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Arshakuni, A. L., and G. P. Mel'nikov. "Choice of kinetic creep equations under irradiation conditions." Strength of Materials 19, no. 6 (June 1987): 810–12. http://dx.doi.org/10.1007/bf01522837.

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