Добірка наукової літератури з теми "Irradiation creep"
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Статті в журналах з теми "Irradiation creep"
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.
Повний текст джерелаZhu, 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.
Повний текст джерелаMartin, J. L. "Creep and microstructure under irradiation." Radiation Effects 101, no. 1-4 (January 1987): 199–200. http://dx.doi.org/10.1080/00337578708224748.
Повний текст джерелаMatthews, 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.
Повний текст джерелаBurchell, 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.
Повний текст джерелаAntipov, 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.
Повний текст джерелаGorokhov, 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.
Повний текст джерелаKarlsen, 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.
Повний текст джерелаBystrov, 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.
Повний текст джерелаPouchon, 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.
Повний текст джерелаДисертації з теми "Irradiation creep"
Salerni, Ronie. "Continuous UV irradiation process for producing low-creep polyethylene." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1996. http://www.collectionscanada.ca/obj/s4/f2/dsk3/ftp04/MQ45468.pdf.
Повний текст джерелаLapouge, Pierre. "Etude expérimentale du fluage d'irradiation dans les métaux et alliages grâce au couplage de la technologie MEMS et d’irradiations aux particules chargées." Thesis, Université Grenoble Alpes (ComUE), 2016. http://www.theses.fr/2016GREAI082/document.
Повний текст джерелаStructural materials used in the PWR cores, such as austenitic stainless steels or zirconium alloys, are exposed to a significant neutron flux and, at the same time, a stress from various mechanical loadings. At the macroscopic scale, the mechanical behavior under irradiation is well characterized. However, at a microscopic scale, the deformation mechanisms under irradiation still remain unknown. Many irradiation creep mechanisms have been proposed from a theoretical point of view but the available experimental data have not, for now, permitted to identify the relevant mechanism leading to the deformation.The objective of this thesis is precisely to improve our understanding of the irradiation creep mechanisms of metals and alloys by the development of a novel experimental method. In this method, the irradiation is produced by the use of heavy ions. This kind of irradiation has the advantage of a fast damage rate without an activation of the material. However the irradiated area is confined in a few hundreds of nanometers. Such thickness requires a specific experimental device to apply a stress on the specimen. This device is based on the release of internal stress in a silicon nitride film to deform a metallic thin film. This method was designed and developed at the Université Catholique de Louvain in Belgium by the teams of Thomas Pardoen and Jean-Pierre Raskin.After proving the feasibility of the study and adapting the device to the irradiation environment, the method has been used with success to reproduce an irradiation creep experiment at room temperature on a model material : copper. A single creep power law with a stress exponent of 5 has been found under irradiation on 200 and 500 nm thick films. The SEM and TEM observations suggest that the deformation mechanism rely on the glide of dislocations assisted by climb.This law seems to be independent of the microstructure and the loading history. The dislocation climb, if it occurs, would not be controlled by diffusion process at long distance but by direct interaction between displacement cascades and dislocations.The mechanical behavior of unirradiated and irradiated copper films have also been assessed. The deformation mechanisms seem to be the same in both cases. At a moderate strain rate, the deformation is controlled by the intragrannular glide of dislocations whereas at slow strain rate a change of mechanism takes place. The new mechanism still remains based on dislocations but a component of grain boundary sliding may appear. A post irradiation hardening has been observed on a 200 nm thick film due to the presence, in the irradiated samples, of a high density of SFT which act as obstacles against dislocation glide
Villani, Aurélien. "Modélisation multiphysique de l'endommagement par irradiation de laminés nanocristallins." Thesis, Paris, ENMP, 2015. http://www.theses.fr/2015ENMP0002/document.
Повний текст джерелаRadiation damage is known to lead to material failure and thus is of critical importance to lifetime and safety within nuclear reactors.While mechanical behaviour of materials under irradiation has been the subject of numerous studies, the current predictive capabilities of such phenomena appear limited.The clustering of point defects such as vacancies and self interstitial atoms gives rise to creep, void swelling and material embrittlement.Nanoscale metallic multilayer systems have be shown to have the ability to evacuate such point defects, hence delaying the occurrence of critical damage.In addition, they exhibit outstanding mechanical properties.The objective of this work is to develop a thermodynamically consistent continuum framework at the meso and nano-scales, which accounts for the major physical processes encountered in such metallic multilayer systems and is able to predict their microstuctural evolution and behavior under irradiation.Mainly three physical phenomena are addressed in the present work: stress-diffusion coupling and diffusion induced creep, the void nucleation and growth in multilayer systems under irradiation, and the interaction of dislocations with the multilayer interfaces.In this framework, the microstructure is explicitly modeled, in order to account accurately for their effects on the system behavior.The diffusion creep strain rate is related to the gradient of the vacancy flux.A Cahn-Hilliard approach is used to model void nucleation and growth, and the diffusion equations for vacancies and self interstitial atoms are complemented to take into account the production of point defects due to irradiation cascades, the mutual recombination of defects and their evacuation through grain boundaries.In metallic multilayers, an interface affected zone is defined, with an additional slip plane to model the interface shearable character, and where dislocations cores are able to spread.The model is then implemented numerically using the finite elements method.Simulations of biaxial creep of polycrystalline aggregates coupled with vacancy diffusion are performed for the first time, and predict strongly heterogeneous viscoplastic strain fields.The classical macroscopic strain rate dependence on the stress and grain size is also retrieved.Void denuded zones close to the multilayer interfaces are obtained in irradiation simulations of a multilayer, in agreement with experimental observations.Finally, tensile tests of Cu-Nb multilayers are simulated in 3D, where it is shown that the effect of elastic anisotropy is negligible, and evidencing a complex deformation mode
Ozaltun, Hakan. "An Energy Based Fatigue Lifing Method for In-Service Components and Numerical Assessment of U10Mo Alloy Based Fuel Mini Plates." The Ohio State University, 2011. http://rave.ohiolink.edu/etdc/view?acc_num=osu1309210033.
Повний текст джерелаMIKOU, MOHAMMED. "Defauts crees par irradiation aux ions lourds rapides dans l'arseniure de gallium : etude par effet hall et photoluminescence." Caen, 1995. http://www.theses.fr/1995CAEN2018.
Повний текст джерелаBERNARD-LABARRE, MONIQUE. "Etude des defauts crees par irradiation dans les halogenures alcalino-terreux et alcalins : centres de type v dans les iodures et les bromures." Nantes, 1995. http://www.theses.fr/1995NANT2029.
Повний текст джерелаFITTE, REY JACQUES. "Determination de la fonction de distribution spatiale et des parametres de photo-ionisation des photo-electrons crees par irradiation vuv de dielectriques liquides non polaires." Toulouse 3, 1998. http://www.theses.fr/1998TOU30150.
Повний текст джерелаSmith, Richard Whiting. "Microstructural modeling of irradiation creep and swelling in single crystal nickel." 1985. http://catalog.hathitrust.org/api/volumes/oclc/68787596.html.
Повний текст джерелаКниги з теми "Irradiation creep"
Salerni, Ronie. Continuous UV irradiation process for producing low creep polyethylene. Ottawa: National Library of Canada, 1996.
Знайти повний текст джерелаCausey, A. R. Irradiation-enhanced creep of cold-worked Zr-2.5Nb tubes and helical-springs. Chalk River, Ont: Reactor Materials Research Branch, Chalk River Laboratories, 1993.
Знайти повний текст джерелаAnsari, Iqbal. Irradiation-Induced Creep and Microstructural Development in Precipitation-Hardened Nickel-Aluminum Alloys. Julich, W. Ger: Zentralbibliothek der Kernforschungsanlage, 1985.
Знайти повний текст джерелаSamoorganizat︠s︡ii︠a︡ v radiat︠s︡ionnoĭ fizike. Kiev: OOO "Vydavnyt︠s︡tvo 'Aspekt-Polīhraf'", 2004.
Знайти повний текст джерелаScholz, R. Light Ion Irradiation Creep in Torsion. European Communities / Union (EUR-OP/OOPEC/OPOCE), 1988.
Знайти повний текст джерела1951-, Christodoulou Nicholas C., ed. Modelling irradiation creep of zirconium alloys. Chalk River, Ont: Reactor Materials Research Branch, Chalk River Laboratories, 1993.
Знайти повний текст джерелаSch<129>le, W., H. Hausen, and M. R. Cundy. Irradiation Creep Experiments on Fusion Reactor Candidate Structural Materials. European Communities / Union (EUR-OP/OOPEC/OPOCE), 1991.
Знайти повний текст джерелаHardt, P. Von Der. Measurement of Irradiation-Enhanced Creep in Nuclear Materials: Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, the Netherlands, May 5-6 1976. Elsevier Science & Technology Books, 2016.
Знайти повний текст джерелаЧастини книг з теми "Irradiation creep"
Was, Gary S. "Irradiation Creep and Growth." In Fundamentals of Radiation Materials Science, 735–91. New York, NY: Springer New York, 2016. http://dx.doi.org/10.1007/978-1-4939-3438-6_13.
Повний текст джерелаGriffiths, M., G. A. Bickel, R. DeAbreu, and W. Li. "Irradiation Creep of Zr-Alloys." In Mechanical and Creep Behavior of Advanced Materials, 165–82. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-51097-2_13.
Повний текст джерелаMurakami, S., and M. Mizuno. "Mechanical Modeling of Irradiation Creep and its Application to the Analysis of Creep Crack Growth." In Creep in Structures, 237–52. Berlin, Heidelberg: Springer Berlin Heidelberg, 1991. http://dx.doi.org/10.1007/978-3-642-84455-3_29.
Повний текст джерелаNishiura, T., S. Nishijima, K. Katagiri, T. Okada, J. Yasuda, and T. Hirokawa. "Creep Test of Composite Materials Under Irradiation Condition." In 11th International Conference on Magnet Technology (MT-11), 708–13. Dordrecht: Springer Netherlands, 1990. http://dx.doi.org/10.1007/978-94-009-0769-0_122.
Повний текст джерелаNishiura, T., S. Nishijima, S. Ueno, Y. Tsukasaki, and T. Okada. "Enhanced Creep of Epoxy Resin During Irradiation at Cryogenic Temperatures." In Advances in Cryogenic Engineering Materials, 291–97. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4757-9056-6_39.
Повний текст джерелаFoster, John Paul, and Rita Baranwal. "ZIRLO® Irradiation Creep Stress Dependence in Compression and Tension." In Zirconium in the Nuclear Industry: 16th International Symposium, 853–74. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2011. http://dx.doi.org/10.1520/stp49286t.
Повний текст джерелаFoster, John Paul, and Rita Baranwal. "ZIRLO® Irradiation Creep Stress Dependence in Compression and Tension." In Zirconium in the Nuclear Industry: 16th International Symposium, 853–74. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2011. http://dx.doi.org/10.1520/stp49384s.
Повний текст джерелаFoster, John Paul, and Rita Baranwal. "ZIRLO® Irradiation Creep Stress Dependence in Compression and Tension." In Zirconium in the Nuclear Industry: 16th International Symposium, 853–74. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2011. http://dx.doi.org/10.1520/stp152920120034.
Повний текст джерелаKumar, N., A. Alsabbagh, C. S. Seok, and K. L. Murty. "Synergistic Effects of Neutron Irradiation and Interstitial Nitrogen on Strain Aging in Ferritic Steels." In Mechanical and Creep Behavior of Advanced Materials, 151–64. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-51097-2_12.
Повний текст джерелаGarzarolli, F., P. Dewes, S. Trapp-Pritsching, and J. L. Nelson. "Irradiation Creep Behavior of High-Purity Stainless Steels and Ni-Base-Alloys." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1027–34. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch107.
Повний текст джерелаТези доповідей конференцій з теми "Irradiation creep"
Yao, Huan, Tianzhou Ye, Junmei Wu, Yingwei Wu, Chunyu Yin, and Ping Chen. "Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-89079.
Повний текст джерелаFedorov, Alexander, Kevin Zwijsen, and Sander van Til. "Modelling of the H2020 INSPYRE Fuel Creep Experiment." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16231.
Повний текст джерелаFang, Xiang, Haitao Wang, and Suyuan Yu. "Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30359.
Повний текст джерелаUENO, KEIKO, JOHSEI NAGAKAWA, NORIKAZU YAMAMOTO, and YOSHIHARU MURASE. "EFFECT OF DISLOCATION ON THE IRRADIATION CREEP OF SUS 316L." In Proceedings of the Seventh China–Japan Symposium. WORLD SCIENTIFIC, 2003. http://dx.doi.org/10.1142/9789812705198_0053.
Повний текст джерелаHattar, Khalid, Eric Lang, and Shen Dillon. "Irradiation Creep and Fatigue Observed via In-situ Electron Microscopy." In Proposed for presentation at the MiNES 21: Materials in Nuclear Energy Systems 2021 held November 8-12, 2021 in Pittsburgh, PA US. US DOE, 2021. http://dx.doi.org/10.2172/1899488.
Повний текст джерелаMargolin, B. Z., A. G. Gulenko, and A. A. Buchatsky. "Prediction of Creep-Rupture Properties for Austenitic Steels Undergone Neutron Irradiation." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77084.
Повний текст джерелаSprouster, D., L. Snead, Y. Katoh, and T. Koyanagi. "X-Ray Characterization of Atomistic Defects Causing Irradiation Creep of SiC." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33154.
Повний текст джерелаJang, Young Ki, Kyeong Lak Jeon, Jae Ik Kim, Jung Cheol Shin, Yong Hwan Kim, Sun Tack Hwang, Man Soo Kim, Tae Hyoung Lee, Yong Bae Yoon, and Tae Wan Kim. "Irradiation Performance Update on Advanced Nuclear Fuel of PLUS7™." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57927.
Повний текст джерелаXiao, Hongxing, Chongsheng Long, Le Chen, and Bo Liang. "Behavior of the Ag-In-Cd Alloy Control Rod Under Irradiation." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15857.
Повний текст джерелаBONDARENKO, A. V., A. A. PRODAN, YU T. PETRUSENKO, V. N. BORISENKO, F. DWORSCHAK, and U. DEDEK. "EFFECT OF ELECTRON IRRADIATION ON ANISOTROPY OF VORTEX CREEP IN YBCO SINGLE CRYSTALS." In Proceedings of the First Regional Conference. World Scientific Publishing Company, 2000. http://dx.doi.org/10.1142/9789812793676_0063.
Повний текст джерелаЗвіти організацій з теми "Irradiation creep"
Ubic, Rick, Darryl Butt, and William Windes. Irradiation Creep in Graphite. Office of Scientific and Technical Information (OSTI), March 2014. http://dx.doi.org/10.2172/1128528.
Повний текст джерелаKennedy, C. R. (Irradiation creep of graphite). Office of Scientific and Technical Information (OSTI), December 1990. http://dx.doi.org/10.2172/6410826.
Повний текст джерелаWas, Gary S., and Anne Campbell. Proton Irradiation Creep in Pyrocarbon. Office of Scientific and Technical Information (OSTI), October 2011. http://dx.doi.org/10.2172/1236831.
Повний текст джерелаTsai, H., M. C. Billone, R. V. Strain, D. L. Smith, and H. Matsui. Irradiation creep of vanadium-base alloys. Office of Scientific and Technical Information (OSTI), March 1998. http://dx.doi.org/10.2172/335380.
Повний текст джерелаWindes, William E., David T. Rohrbaugh, and W. David Swank. AGC 2 Irradiation Creep Strain Data Analysis. Office of Scientific and Technical Information (OSTI), August 2016. http://dx.doi.org/10.2172/1374497.
Повний текст джерелаWindes, William E., David T. Rohrbaugh, and W. David Swank. AGC 3 Irradiation Creep Strain Data Analysis. Office of Scientific and Technical Information (OSTI), July 2019. http://dx.doi.org/10.2172/1599770.
Повний текст джерелаTsai, H., R. V. Strain, and D. L. Smith. Study of irradiation creep of vanadium alloys. Office of Scientific and Technical Information (OSTI), August 1997. http://dx.doi.org/10.2172/543201.
Повний текст джерелаPokrovsky, A. S., V. R. Barabash, and S. A. Fabritsiev. Irradiation creep of dispersion strengthened copper alloy. Office of Scientific and Technical Information (OSTI), April 1997. http://dx.doi.org/10.2172/543294.
Повний текст джерелаKelly, B. T. The Analysis of Irradiation Creep in Reactor Graphite. Office of Scientific and Technical Information (OSTI), June 1993. http://dx.doi.org/10.2172/1366725.
Повний текст джерелаWoo, C. H., and F. A. Garner. Contribution to irradiation creep arising from gas-driven bubbles. Office of Scientific and Technical Information (OSTI), March 1998. http://dx.doi.org/10.2172/335410.
Повний текст джерела