Academic literature on the topic 'Radiation effects on alloys'

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Journal articles on the topic "Radiation effects on alloys"

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Barbu, Alain, and G. Martin. "Radiation Effects in Metals and Alloys." Solid State Phenomena 30-31 (January 1992): 179–228. http://dx.doi.org/10.4028/www.scientific.net/ssp.30-31.179.

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Stopher, M. A. "The effects of neutron radiation on nickel-based alloys." Materials Science and Technology 33, no. 5 (June 29, 2016): 518–36. http://dx.doi.org/10.1080/02670836.2016.1187334.

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Mukashev, Kanat Mukashevich, and Farid Fahrievich Umarov. "RADIATION-INDUCED EFFECTS AND DEFECTS IN TI -GE ALLOYS." Theoretical & Applied Science 29, no. 09 (September 30, 2015): 144–48. http://dx.doi.org/10.15863/tas.2015.09.29.28.

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Azeem, M. Mustafa, Muhammad Zubair, Mohammad Ado, K. Abd El Gawad, Shehu Adam Ibrahim, and Ghazanfar Mehdi. "RADIATION DAMAGE EFFECTS IN OXIDE DISPERSION STRENGTHENED STEEL ALLOYS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27 (2019): 2086. http://dx.doi.org/10.1299/jsmeicone.2019.27.2086.

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Aydogan, E., J. G. Gigax, S. S. Parker, B. P. Eftink, M. Chancey, J. Poplawsky, and S. A. Maloy. "Nitrogen effects on radiation response in 12Cr ferritic/martensitic alloys." Scripta Materialia 189 (December 2020): 145–50. http://dx.doi.org/10.1016/j.scriptamat.2020.08.005.

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Khaskin, V. Yu, V. N. Korzhik, T. G. Chizhskaya, V. N. Sidorets, and Lo Zie. "Effect of laser radiation absorption on efficiency of laser welding of copper and its alloys." Paton Welding Journal 2016, no. 11 (November 28, 2016): 31–35. http://dx.doi.org/10.15407/tpwj2016.11.05.

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Shalaev, A. M., V. V. Kotov, V. V. Polotnjuk, and I. N. Makeeva. "The Temperature and Radiation Effects on a Local Order of Amorphous Alloys." Key Engineering Materials 40-41 (January 1991): 267–74. http://dx.doi.org/10.4028/www.scientific.net/kem.40-41.267.

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Fabritsiev, S. A., A. S. Pokrovskii, V. R. Barabash, and Y. G. Prokofiev. "Neutron spectrum and transmutation effects on the radiation damage of copper alloys." Fusion Engineering and Design 36, no. 4 (July 1997): 505–13. http://dx.doi.org/10.1016/s0920-3796(96)00700-4.

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Mansur, L. K. "Theory of transitions in dose dependence of radiation effects in structural alloys." Journal of Nuclear Materials 206, no. 2-3 (November 1993): 306–23. http://dx.doi.org/10.1016/0022-3115(93)90130-q.

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Onimus, F., J. L. Béchade, C. Duguay, D. Gilbon, and P. Pilvin. "Investigation of neutron radiation effects on the mechanical behavior of recrystallized zirconium alloys." Journal of Nuclear Materials 358, no. 2-3 (November 2006): 176–89. http://dx.doi.org/10.1016/j.jnucmat.2006.07.005.

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Dissertations / Theses on the topic "Radiation effects on alloys"

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Perks, Jonathan Michael. "Phosphorus segregation and diffusion in nickel and Fe-Cr-Ni alloys under fast particle irradiation." Thesis, University of Oxford, 1988. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.329993.

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Terentyev, Dmitry. "Study of radiation effects in FeCr alloys for fusion applications using computer simulations." Doctoral thesis, Universite Libre de Bruxelles, 2006. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/210787.

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Galloway, Graham. "Computational study of radiation damage and impurity effects in iron based alloys." Thesis, University of Edinburgh, 2014. http://hdl.handle.net/1842/9908.

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Molecular dynamics techniques are used to explore metals at an atomic level. The focus of the studies is the effects of irradiation on a metallic system. Ion surface bombardment effects, bulk cascades and interaction with voids and bubbles in bulk are studied. In the first section a study of a copper <110> surface being bombarded by low energy argon ions is conducted. Molecular dynamics simulations were used to study the surface impact crater formation and the damage caused in the surrounding area. Another group had previously performed experimental measurements on the same system. The simulation data is compared to experiment, in order to validate the molecular dynamics technique. Additionally, information about the formation of the craters at time scales inaccessible to experiment can be gained. In the next section bulk radiation induced cascades in BCC iron are considered. Cascades of energy 1 keV, 2 keV, and 5 keV are initiated in the bulk of the material and the damage yields studied. Cascades are also studied in proximity to voids and helium bubbles in the bulk. The damage formation processes and damage yields in these cascades is analysed. A mechanism that allowed voids to be ballistically moved by the cascade was observed. To further explore this an object kinetic Monte Carlo model was written to simulate the effects of this motion on the diffusion of the voids. The final section is a study of transition metals as alloying elements in BCC iron. This system is of interest as it would be a model for various steels used in construction and shielding. A set of potentials describing iron with low concentrations of transition metals has previously been developed by a different group. These potentials were implemented in the molecular dynamics code. The equilibrium properties of various alloys are explored by implementing a Metropolis algorithm to minimise the Gibbs free energy of the system. Various binary and tertiary alloys are analysed and compared with experimental values in the literature. The attraction of the elements to voids present in the system is also studied.
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Huang, Liangzhao. "Multiscale modeling of the radiation-induced segregation in Ni-based and Fe-based dilute alloys." Thesis, université Paris-Saclay, 2020. http://www.theses.fr/2020UPASP048.

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Nous présentons une modélisation quantitative de la redistribution des défauts ponctuels (DPs) et de la ségrégation induite par irradiation (SII) sur les défauts étendus, dans des alliages modèles dilués Ni(B ≡ Ti, Cr) et Fe(B ≡ P, Mn, Cr, Si, Ni, Cu). Le changement de composition chimique au voisinage des défauts étendus joue un rôle décisif sur l’évolution de la microstructure et les propriétés mécaniques d’un matériau. L’irradiation génère des défauts ponctuels, qui diffusent en s’échangeant avec les atomes voisins, s’annihilent en se recombinant entre eux ou en interagissant avec des défauts étendus (qui agissent comme des puits de DPs). Les flux de DPs vers les puits induisent des flux atomiques dans le même sens ou le sens opposé des flux de DPs, produisant ainsi la SII aux puits. Nous étendons la théorie de champ moyen auto-cohérent aux déplacements atomiques forcés (DAF), mécanismes de diffusion athermiques générés par une cascade de déplacements sous irradiation. L’implémentation de nos développements théoriques dans le code KineCluE, nous permet de calculer les flux de DPs et d’atomes, et leurs couplages. A partir du calcul des flux en fonction de la température, de la composition, et du champ de déformation ; et d’un traitement de type cinétique chimique des réactions de production et d’annihilation des DPs, nous obtenons les profils stationnaires de SII. Dans chacun des régimes cinétiques particuliers pour lequel, l’une des réactions des DPs domine par rapport aux autres, nous obtenons les expressions analytiques des profils stationnaires des DPs et solutés sur les puits planaires. Pour rendre compte de l’effet du champ de déformation généré par une dislocation coin sur la SII et sur les taux d’élimination des DPs sur la dislocation, nous résolvons numériquement les équations d’élastodiffusion. A partir d’une base de données ab initio des énergies de liaison, des dipôles élastiques, et des fréquences d’échange atome-DP dans, nous réalisons une étude systématique des effets de la microstructure et des conditions d’irradiation sur les propriétés de diffusion, les taux d’élimination des DPs aux puits, et la SII. Nous montrons que : (i) les boucles de dislocations sont enrichies en Ni dans Fe(Ni) et appauvries en Ti dans Ni(Ti), et les quantités ségrégées sont en bon accord avec les valeurs expérimentales mesurées dans les alliages modèles Fe(Ni) et Ni(Ti) irradiés aux ions ; (ii) à fort flux, basse température, et grande force de puits de la microstructure, les évènements DAF réduisent sensiblement la SII, tout particulièrement dans les alliages base Ni ; (iii) les décalages en température calculés pour simuler les effets d’une irradiation aux neutrons par une irradiation aux ions, peuvent être très différents selon le phénomène induit par irradiation que l’on étudie, le régime cinétique dans lequel le système évolue, et la nature chimique de l’alliage étudié ; (iv) l’interaction entre les DPs et les atomes de soluté modifie le facteur de biais d’absorption entre lacunes et interstitiels d’une dislocation coin. Ainsi l’ajout de Ni produit un biais négatif alors que l’ajout de Mn augmente le facteur de biais (jusqu’à 200% de la valeur dans Fe pur sous contrainte), suivant la température et la composition ; (v) la contrainte augmente significativement la quantité de la ségrégation de soluté dans Fe(Ni) (par exemple, 400% de la valeur sans élasticité à 400K), et change le signe de la SII dans Fe(Cr)
We present a quantitative modeling of the point-defect (PD) redistribution and solute radiation-induced segregation (RIS) at extended defects in dilute Ni(B ≡ Ti, Cr) and Fe(B ≡ P, Mn, Cr, Si, Ni, Cu) alloys. The change in chemical composition, in the vicinity of extended defects, plays a decisive role on the evolution of the microstructure and mechanical properties of materials. Irradiation produces PDs, that diffuse by exchanging with neighboring atoms, annihilate by mutual recombination or by interacting with extended defects (that act as PD sinks). The fluxes of PDs towards sinks lead to atomic fluxes in the same or opposite direction of the PD flux; thereby producing RIS at sinks. We extend the self-consistent mean-field theory to forced atomic relocations (FARs), athermal diffusion mechanisms generated by displacement cascades under irradiation. The implementation of the extended theory in the KineCluE code allows us to compute PD and atomic fluxes, and their couplings. From the calculation of fluxes as a function of temperature, composition, and strain field; and a mean-field treatment of the production and annihilation reactions of PDs, we obtain the steady-state RIS profiles. In each of the particular kinetic regimes for which one of the PD reactions dominates over the others, we derive analytical expressions of steady-state profiles of PDs and solute atoms at planar sinks. To account for the effect of strain generated by an edge dislocation on the RIS and PD elimination rates, we numerically solve the elastodiffusion equations. Based on an ab initio database of binding energies, elastic dipoles, and atom-PD exchange frequencies, we perform a systematic study of the effects of the microstructure and irradiation conditions on diffusion properties, PD elimination rates at sinks, and RIS. We show that: (i) the dislocation loops are enriched in Ni in Fe(Ni) and depleted in Ti in Ni(Ti), and the calculated amounts of RIS are in good agreement with the experimental values measured in model Fe(Ni) and Ni(Ti) alloys irradiated by ions; (ii) at high flux, low temperature, and high sink strength, forced atomic relocations significantly reduce RIS, especially in Ni-based alloys; (iii) the temperature shifts calculated to simulate the effects of neutron irradiation by ion irradiation can be very different depending on the radiation-induced phenomenon, the kinetic regime in which the system evolves, and the chemical nature of the investigated alloy; (iv) the interactions between PDs and solute atoms change the absorption bias between vacancies and interstitials of an edge dislocation, as for instance, the addition of Ni leads to a negative bias while the addition of Mn increases the bias factor (up to 200% of the strained pure Fe value), depending on temperature and composition; (v) the dislocation strain field significantly increases Ni RIS (e.g., about 400% of the strain-free value at 400K) in Fe(Ni), and changes the sign of RIS in Fe(Cr)
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Murphy, Susan Mary. "Theory of compositional effects in irradiation damage." Thesis, University of Oxford, 1987. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.670365.

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Umana-Membreno, Gilberto A. "A study of gamma-radiation-induced effects in gallium nitride based devices." University of Western Australia. School of Electrical, Electronic and Computer Engineering, 2006. http://theses.library.uwa.edu.au/adt-WU2007.0015.

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[Truncated abstract] Over the past decade, the group III-nitride semiconducting compounds (GaN, AlN, InN, and their alloys) have attracted tremendous research efforts due to their unique electronic and optical properties. Their low thermal carrier generation rates and large breakdown fields make them attractive for the development of robust electronic devices capable of reliable operation in extreme conditions, i.e. at high power/voltage levels, high temperatures and in radiation environments. For device applications in radiation environments, such as space electronics, GaN-based devices are expected to manifest superior radiation hardness and reliability without the need for cumber- some and expensive cooling systems and/or radiation shielding. The principle aim of this Thesis is to ascertain the level of susceptibility of current GaN-based elec- tron devices to radiation-induced degradation, by undertaking a detailed study of 60Co gamma-irradiation-induced defects and defect-related effects on the electrical characteristics of n-type GaN-based materials and devices . . . While the irradiation-induced effects on device threshold voltage could be regarded as relatively benign (taking into account that the irradiation levels employed in this study are equivalent to more than 60 years exposure at the average ionising dose rate levels present in space missions), the observed device instabilities and the degradation of gate current characteristics are deleterious effects which will have a significant impact on the performance of AlGaN/GaN HEMTs operating in radiation environments at low temperatures, a combination of conditions which are found in spaceborne electronic systems.
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Piochaud, Jean-Baptiste. "Modelling of radiation induced segregation in austenitic Fe alloys at the atomistic level." Thesis, Lille 1, 2013. http://www.theses.fr/2013LIL10024/document.

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Dans les réacteurs à eaux pressurisée, les internes de cuve sont soumis à d’intenses irradiations induisant le mécanisme de corrosion sous contrainte assistée par l’irradiation initié par le phénomène de ségrégation induite par l’irradiation (SIR). La SIR observée dans les aciers austénitiques 316 est modélisée à l’échelle atomique en considérant un alliage ternaire modèle Fe–10Ni–20Cr. Pour atteindre cet objectif, nous avons construit un modèle d’interactions de paires pour le système Fe-Ni-Cr afin de modéliser la SIR par méthodes Monte Carlo. Le modèle d’interactions de paires fut déduit à la fois des calculs DFT (Density Functional Theory) disponibles dans les systèmes pures cubiques faces centrées, mais aussi en effectuant des calculs DFT dans l’alliage Fe–10Ni–20Cr. Les énergies de formation calculées dans cet alliage modèle dépendent fortement de l’environnement local des défauts ponctuels. Nous avons pu ainsi établir une relation liant ces énergies au nombre et à la position des atomes de Ni et de Cr se trouvant à proximité des défauts ponctuels. Dans cette étude, nous montrons qu’un modèle d’interactions de paires uniquement basé sur les interactions entre éléments positionnés sur les sites du réseau (éléments d’alliage et lacune) est incapable de prendre en compte seul à la fois les aspects thermodynamiques et cinétiques de la SIR. Une estimation plus précise des barrières de migration est requise pour les espèces migrantes que celle proposée qui ne prend pas en compte l’environnement du point col. Ce travail montre ainsi qu’il est nécessaire de réaliser des calculs DFT des énergies de migration afin d’être en mesure de calibrer un modèle utilisable dans le cadre de simulations de Monte Carlo cinétique atomique. Nous montrons également que l’ajustement de notre modèle sur les données DFT obtenues pour les interstitiels est incompatible avec la modélisation de la SIR aux électrons
In pressurized water reactors, under irradiation internal structures are subject of irradiation assisted stress corrosion cracking which is influenced by radiation induced segregation (RIS). In this work RIS of 316 stainless steels is modelled considering a model ternary Fe–10Ni–20Cr alloy. For this purpose we have built an Fe-Ni-Cr pair interaction model to simulate RIS at the atomistic level using an atomistic kinetic Monte Carlo approach. The pair interactions have been deduced from density functional theory (DFT) data available in the pure fcc systems but also from DFT calculations we have performed in the Fe–10Ni–20Cr target alloy. Point defect formation energies were calculated and found to depend strongly on the local environment of the defect. As a consequence, a rather good estimation of these energies can be obtained from the knowledge of the number and respective positions of the Ni and Cr atoms in the vicinity of the defect. This work shows that a model based only on interaction parameters between elements positioned in perfect lattice sites (solute atoms and vacancy) cannot capture alone both the thermodynamic and the kinetic aspect of RIS. A more accurate of estimating the barriers encountered by the diffusing species is required than the one used in our model, which has to depend on the saddle point environment. This study therefore shows thus the need to estimate point defect migration energies using the DFT approach to calibrate a model that can be used in the framework of atomic kinetic Monte Carlo simulations. We also found that the reproduction by our pair interaction model of DFT data for the self-interstitial atoms was found to be incompatible with the modelling of RIS under electron irradiation
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Diestelhorst, Ryan M. "Silicon-germanium BiCMOS device and circuit design for extreme environment applications." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2009. http://hdl.handle.net/1853/28180.

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Thesis (M. S.)--Electrical and Computer Engineering, Georgia Institute of Technology, 2009.
Committee Chair: Cressler, John; Committee Member: Papapolymerou, John; Committee Member: Ralph, Stephen.
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Choi, Hong Kyu. "Analysis and modeling of the long-term performance of amorphous photovoltaic arrays." Diss., The University of Arizona, 1989. http://hdl.handle.net/10150/184835.

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A validated predictive model of a-Si:H solar cell arrays was developed. The performance of a-Si:H solar cells was modeled by predicting the performance before degradation first, and then modifying it with terms that account for degradation and recovery effects. A unique approach for the determination of the fundamental rate controlling parameters for the degradation and recovery process was carried out by observing the variation of the short-circuit current. The experimental annealing of a-Si:H silicon samples showed that the percent recovery from the degraded state to the as-grown state by annealing was virtually independent of the initial state at the start of the annealing process. This allowed the recovery parameters to be determined independently of the prior degradation process. An extremely simple and fast running algorithm for the long-term performance was developed in terms of the incident solar radiation, the panel temperature, and the total radiation exposed. Also it was found that the entire process of the Staebler-Wronski effect could be adequately represented by a correlation in which the degradation and recovery processes are solely a function of the total radiation exposure of the panel at ambient conditions.
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Lourenco, Nelson Estacio. "An assessment of silicon-germanium BiCMOS technologies for extreme environment applications." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/45959.

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This thesis evaluates the suitability of silicon-germanium technology for electronic systems intended for extreme environments, such as ambient temperatures outside of military specification (-55 degC to 125 degC) range and intense exposures to ionizing radiation. Silicon-germanium devices and circuits were characterized at cryogenic and high-temperatures (up to 300 degC) and exposed to ionizing radiation, providing empirical evidence that silicon-germanium is an excellent platform for terrestrial and space-based electronic applications.
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Books on the topic "Radiation effects on alloys"

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Koutský, Jaroslav. Radiation damage of structural materials. Amsterdam: Elsevier, 1994.

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Koutsk'y, Jaroslav. Radiation damage of structural materials. Amsterdam: Elsevier, 1994.

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Huang, F. H. Fracture properties of irradiated alloys. Richland, WA: Avante Pub., 1995.

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Nembach, E. Particle strengthening of metals and alloys. New York: Wiley, 1997.

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Shalaev, A. M. Svoĭstva obluchennykh metallov i splavov. Kiev: Nauk. dumka, 1985.

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Sh, Ibragimov Sh. Radiat͡s︡ionnye povrezhdenii͡a︡ metallov i splavov. Moskva: Ėnergoatomizdat, 1985.

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Didenko, Andreĭ Nikolaevich. Vozdeĭstvie puchkov zari͡a︡zhennykh chastit͡s︡ na poverkhnostʹ metallov i splavov. Moskva: Ėnergoatomizdat, 1987.

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Konferent͡sii͡a "Modifikat͡sii͡a konstrukt͡sionnykh materialov puchkami zari͡azhennykh chastit͡s" (3rd 1994 Tomsk, Russia). III konferent͡sii͡a ʺModifikat͡sii͡a svoĭstv konstrukt͡sionnykh materialov puchkami zari͡azhennykh chastit͡sʺ: Tomsk, 8-10 fevrali͡a 1994 g. Tomsk: SO RAN, 1994.

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E, Kreĭndelʹ I͡U, Ovchinnikov V. V, Nauchnyĭ sovet GKNT SSSR i AN SSSR po probleme "Obrabotka konstrukt͡sionnykh materialov puchkami zari͡azhennykh chastit͡s.", and Institut ėlektrofiziki (Akademii͡a nauk SSSR), eds. Modifikat͡sii͡a svoĭstv konstrukt͡sionnykh materialov puchkami zari͡azhennykh chastit͡s: II Vsesoi͡uznai͡a conferent͡sii͡a, Sverdlovsk, 21-24 mai͡a 1991 g. : tezisy dokladov. Sverdlovsk: UrO AN SSSR, 1991.

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Srivastava, D., and Dinesh Srivastava. Microstructural examination of Zr-2.5%Nb pressure tube S-07 from Kakrapar atomic power station unit-2. Mumbai: Bhabha Atomic Research Centre, 2011.

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Book chapters on the topic "Radiation effects on alloys"

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Judge, C. D., M. Griffiths, L. Walters, M. Wright, G. A. Bickel, O. T. Woo, M. Stewart, S. R. Douglas, and F. A. Garner. "Embrittlement of Nickel Alloys in a CANDU Reactor Environment." In Effects of Radiation on Nuclear Materials: 25th Volume, 161–75. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp104242.

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Murugan, S., P. V. Kumar, Jojo Joseph, S. Venugopal, T. Jayakumar, and Baldev Raj. "Irradiation Testing of Zirconium Alloys and Stainless Steel in Fast Breeder Test Reactor, India." In Effects of Radiation on Nuclear Materials: 25th Volume, 176–91. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp104027.

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Savino, Eduardo J., and Santiago Harriague. "Micro-Macrostructural Mechanical Behavior of Anisotropic Zirconium Alloys Under Irradiation." In Effects of Radiation on Materials: 12th International Symposium Volume II, 667–89. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 1985. http://dx.doi.org/10.1520/stp87019850009.

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Braski, David N., and Dan W. Ramey. "A Modified Tritium Trick Technique for Doping Vanadium Alloys with Helium." In Effects of Radiation on Materials: 12th International Symposium Volume II, 1211–24. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 1985. http://dx.doi.org/10.1520/stp87019850040.

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Hein, Hieronymus, Hilmar Schnabel, and Stephan Welzel. "Material Investigations on Highly Irradiated Aluminum Magnesium Alloys for Lifetime Assessment of a Neutron Beam Tube in the BER II Research Reactor." In Effects of Radiation on Nuclear Materials: 25thVolume, 1–19. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp104128t.

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Hein, Hieronymus, Hilmar Schnabel, and Stephan Welzel. "Material Investigations on Highly Irradiated Aluminum Magnesium Alloys for Lifetime Assessment of a Neutron Beam Tube in the BER II Research Reactor." In Effects of Radiation on Nuclear Materials: 25th Volume, 192–210. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp104128.

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Efsing, Pål, Jenny Roudén, and Per Nilsson. "Flux Effects on Radiation Induced Aging Behaviour of Low Alloy Steel Weld Material with High Nickel and Manganese Content." In Effects of Radiation on Nuclear Materials: 26th Volume, 119–34. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2014. http://dx.doi.org/10.1520/stp157220130112.

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Lim, J. J. H., J. M. Hyde, S. Lozano-Perez, and C. R. M. Grovenor. "Microstructural Characterization of Irradiation-Induced MnNi-Rich Solute Cluster in Highly Neutron-Irradiated MnNiMo Alloyed Weld Metals." In Effects of Radiation on Nuclear Materials: 26th Volume, 57–73. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2014. http://dx.doi.org/10.1520/stp157220130120.

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Kuzmann, E., S. Stichleutner, G. Principi, C. Tosello, M. El-Sharif, C. U. Chisholm, K. Havancsák, et al. "Mössbauer study of radiation effects on swift heavy ion irradiated Fe-Ni-Cr multilayers and electrodeposited alloys." In Hyperfine Interactions (C), 591–94. Dordrecht: Springer Netherlands, 2002. http://dx.doi.org/10.1007/978-94-010-0281-3_145.

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Mingler, B., and H. P. Karnthaler. "Tem Studies of the Early Stages of Precipitation in Al-Mg-Si Alloys in Comparison with Electron Radiation Damage Effects." In Electron Crystallography, 397–400. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-015-8971-0_40.

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Conference papers on the topic "Radiation effects on alloys"

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Zinkle, Steven J. "Radiation Effects in Refractory Alloys." In SPACE TECHNOLOGY AND APPLICATIONS INTERNAT.FORUM-STAIF 2004: Conf.on Thermophys.in Microgravity; Commercial/Civil Next Gen.Space Transp.; 21st Symp.Space Nuclear Power & Propulsion; Human Space Explor.; Space Colonization; New Frontiers & Future Concepts. AIP, 2004. http://dx.doi.org/10.1063/1.1649637.

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Mukashev, Kanat M., Kunsulu S. Shadinova, and Farid F. Umarov. "Radiation-induced effects in titanium alloys by α-particles irradiation." In 2014 20th International Conference on Ion Implantation Technology (IIT). IEEE, 2014. http://dx.doi.org/10.1109/iit.2014.6939981.

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Vardanyan, Eduard, Almaz Nazarov, Rustem Nagimov, Semyon Starovoitov, and Kamil Ramazanov. "Specific Features of Milling Titanium Alloys by Cutting Tools with Different PVD Coatings." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9242037.

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Zaguliaev, Dmitrii, Ilya Chumachkov, Yurii Ivanov, Anna Abaturova, Artem Ustinov, and Alexander Semin. "Analysis of Structure and Microhardness AlSi5Cu2 and AlSi10Cu2 Cast Alloys Subjected to Electron Beam Surface Melting." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9242140.

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Serdobintsev, Alexey, Viktor Galushka, Anton Pavlov, Ilya Kozhevnikov, Andrei Starodubov, Roman Torgashov, and Nikita Ryskin. "Molybdenum-copper Alloys as a Base Material for Microfabrication Planar Slow-wave Structures of Millimeter-band Vacuum Electron Devices." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9241932.

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Shulepov, Ivan, Anton Lomygin, Laptev Roman, Egor Kashkarov, Natalia Narkevich, Maksim Syrtanov, and Larisa Botaeva. "Investigation of the Electronic Structure of Atoms in Modified Metal Alloys in Analysis of the Elastic and Discrete Scattered Electron Spectra." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9242153.

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Terentyev, Dmitry, Giovanni Bonny, and Nicolas Castin. "Aspects of Radiation Damage Effects in Iron-Chromium Alloys From the Point of View of Atomistic Modelling." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75636.

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Abstract:
Fe-Cr alloys are the basis of high-Cr ferritic steels, which are the candidate structural materials for near future power plants. Recently, a significant effort has been put in the development of theoretical models dealing with the response of Fe-Cr alloys to irradiation. Here, we give a brief overview of the current level of understanding of radiation damage in Fe-Cr alloys, based on the most recent results. In particular, we review and summarize data obtained using different atomistic modelling techniques in order to refine the most important findings achieved over the past few years.
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Smirnyagina, Natalia, Dorzho Dasheev, and Aleksandr Milonov. "The Synthesis of Intermetallic Ni3Al on Titanium Alloy VT-6." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9241960.

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Lapina, Anna, and Natalia Smirnyagina. "Thermophysical Model of Electron Beam Boriding of Titanium Alloy VT-1." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9241923.

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Markov, Alexey, Daria Shepel', Andrey Solovyov, Vsevolod Petrov, and Evgenii Yakovlev. "Pulsed Electron-Beam-Assisted Synthesis of a Ni-Al Surface Alloy." In 2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE). IEEE, 2020. http://dx.doi.org/10.1109/efre47760.2020.9242054.

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Reports on the topic "Radiation effects on alloys"

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Johnson, A. B. Jr. Radiation effects on corrosion of zirconium alloys. Office of Scientific and Technical Information (OSTI), June 1989. http://dx.doi.org/10.2172/6316113.

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Mansur, Louis K. Survey of Radiation Effects in Titanium Alloys. Office of Scientific and Technical Information (OSTI), August 2008. http://dx.doi.org/10.2172/969959.

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Dane Morgan. Ab initio Based Modeling of Radiation Effects in Multi-Component Alloys: Final Scientific/Technical Report. Office of Scientific and Technical Information (OSTI), June 2010. http://dx.doi.org/10.2172/981472.

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T Angeliu, J Ward, and J Witter. Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System. Office of Scientific and Technical Information (OSTI), April 2006. http://dx.doi.org/10.2172/881302.

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T. Angeliu. Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System. Office of Scientific and Technical Information (OSTI), January 2006. http://dx.doi.org/10.2172/883660.

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Field, Kevin G., Samuel A. Briggs, Philip Edmondson, Xunxiang Hu, Kenneth C. Littrell, Richard Howard, Chad M. Parish, and Yukinori Yamamoto. Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys. Office of Scientific and Technical Information (OSTI), September 2015. http://dx.doi.org/10.2172/1253237.

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Yang, Ying. Development of Computational Tools for Modeling Thermal and Radiation Effects on Grain Boundary Segregation and Precipitation in Fe-Cr-Ni-based Alloys. Office of Scientific and Technical Information (OSTI), August 2017. http://dx.doi.org/10.2172/1394351.

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XU, Haixuan, Lizhan Tan, Kumar Sridharan, and Li He. Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709. Office of Scientific and Technical Information (OSTI), December 2018. http://dx.doi.org/10.2172/1491736.

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Xu, Haixuan, Lizhen Tan, Li He, and Kumar Sridharan. Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709. Office of Scientific and Technical Information (OSTI), December 2018. http://dx.doi.org/10.2172/1528716.

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Snead, L. L., S. J. Zinkle, D. J. Alexander, A. F. Rowcliffe, J. P. Robertson, and W. S. Eatherly. Summary of the investigation of low temperature, low dose radiation effects on the V-4Cr-4Ti alloy. Office of Scientific and Technical Information (OSTI), March 1998. http://dx.doi.org/10.2172/335368.

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