2 edition of Irradiation Growth of the Intermetallic zr3A1. found in the catalog.
Irradiation Growth of the Intermetallic zr3A1.
Atomic Energy of Canada Limited.
|Series||Atomic Energy of Canada Limited. AECL -- 5961|
|Contributions||Rosinger, H.E., Duncan, R.G.|
irradiation examination results. Development of accident tolerant neutron absorbing materials is a key aspect necessary to ensure theaccident tolerance of the commercial nuclear fleet. Once irradiation of these materials is complete and the results incorporated into designFile Size: 71KB. Influence of injected interstitials on α' precipitation in Fe-Cr alloys under self-ion irradiation O. Tissota,b,, C. Pareigeb, E. Meslinc, B. Decampsd and J. Henrya a DEN-Service de Recherches Métallurgiques Appliquées, Laboratoire d’Analyse Microstructurale des Matériaux, CEA, Université Paris-Saclay, F, Gif-sur-Yvette, France b Normandie Univ, UNIROUEN, .
2nd Int. MINOS Workshop, Irradiation of Nuclear Materials: Flux and Dose Effects November , , CEA – INSTN Cadarache, France Atomistic Modeling of Segregation and Precipitation in Fe-Cr Alloys under Irradiation C.-C. Fu, T. Jourdan, M. Nastar, O. Senninger,File Size: 1MB. Introduction. An initial report on the ability of alloys and intermetallics to form compounds with hydrogen dates back to , when Libowitz1 showed that ZrNi easily and reversibly reacts with hydrogen forming ZrNiH r, the birth of a new field, chemistry of intermetallic hydrides, is usually considered to be coincident with the discovery a decade later of hydrideforming .
LAMMPS Simulation in the Investigation of Dimensional Changes in Zirconium in the Presence of Alloying Elements and Hydrogen* LAMMPS User Group Meeting C. Freeman, P. Saxe, M. Christensen, W. Wolf, D. Rigby, and E. Wimmer *Work performed in collaboration with EPRI. FAO/IAEA Technical Co-operation Projects. The Food and Environmental Protection subprogramme of the Joint FAO/IAEA Programme of Nuclear Techniques in Food and Agriculture transfers nuclear and related technologies to Member States by providing technical and scientific support through Technical Cooperation Projects (TCPs) that are managed by IAEA's .
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In-situ 1 MeV Kr²⁺ heavy ion irradiation was performed in a TEM to study the stability of the intermetallic particles under irradiation and the effects of the intermetallic particle on the.
An intermetallic (also called an intermetallic compound, intermetallic alloy, ordered intermetallic alloy, and a long-range-ordered alloy) is a type of metallic alloy that forms a solid-state compound exhibiting defined stoichiometry and ordered crystal structure.
Although the term "intermetallic compounds", as it applies to solid phases, has been in use for many years, its introduction was. Intermetallic growth is the result of the diffusion of one material into another via crystal vacancies made available by defects, contamination, impurities, grain boundaries and mechanical stress.
The diffusion rate for Au in Al is different than that for Al. Tensile properties of Ti-^7at% Al intermetallic compounds before and after neutron irradiation Yield stress (MPa) Tensile stress (MPa) Total elongation (%) Unirradiated Run 1 Run 2 Average Irradiated Run 1 Run 2 Average 69 1 Ductilization of TiAl Cited by: Irradiation growth measurements have been made on annealed polycrystalline Zr% Sn and Zr% Sn alloy specimens irradiated at and K in the DIDO reactor up to fast neutron fluences of × 10 25 n/m 2 and × 10 25 n/m 2 (E > 1 MeV) respectively.
Breakaway growth is observed in Zr% Sn at both temperatures above a fluence of ~3 × 10 25 n/m 2 Cited by: Irradiation growth, which is defined as irradiationinduced changes in dimensions in the absence of an applied stress, is of concern both for fuel cladding and nuclear reactor structural components such as pressure tubes and calandria tubes.
A critical review is presented of irradiation growth data for zirconium alloys together with a discussion of the various Cited by: 8. The irradiation creep results confirm the improved behavior of RXA Zy-4, M4, and M5 in comparison to that of SRA Zy Similar trends are observed for irradiation growth, the SRA Zy-4 exhibiting a quasi-linear behavior with increasing fluence while RXA alloys undergo an early saturation by: 17 May ASTM Conference, Hilton Head Island, SC –Understanding Irradiation Growth through Atomistic Simulations, 15 Materials Design, Inc.
The circular shape of planar SIA clusters decorated by Fe atoms at the rim could explain the ring-shaped features of Fe found by atom probe tomography (APT) in irradiated Zircaloy-2 by Sundell et al. Two types of samples were applied in this wire-bond evaluation work for an Al-pad diffusion process.
One was finished product for the cross-section examination of wire-bond and the other was without compound encapsulant used for the plane view examination of wire-bond interface.
These samples were aged at C in air from 0 h to h. It is found that the Cited by: PDF | The formation mechanism of intermetallic compounds formed in boron steel hot-dipped in Al–7Ni (wt %) at °С for 10– s was studied by | Find, read and cite all the research you.
Electromigration enhanced intermetallic growth and void formation in Pb-free solder joints Brook Chao,a Seung-Hyun Chae, Xuefeng Zhang, Kuan-Hsun Lu, Min Ding, Jay Im, and Paul S. Ho Laboratory for Interconnect and Packaging, The University of.
Effects of electromigration on the growth of intermetallic compounds in Cu/SnBi/Cu solder joints X. Gu, D. Yang, Y.C. Chan,a) and B.Y.
Wu Department of Electronic Engineering, City University of Hong Kong, Kowloon Tong, Hong Kong, People’s Republic of China (Received 4 January ; accepted 25 March ). Energetic ion irradiation locally gives high density energy deposition into a target, and it can induce non-thermal equilibrium phases.
In our previous results, we showed the ion irradiation induced phase transition for Ni 3V and Ni 3Al intermetallic compounds 1), 2). Ni 3V shows the tetragonal ordered structure (D structure) at room. Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U wt % Mo Fuel Alloy One of reports in the series: AEC research and development report available on this by: 2.
Effects of neutron and gamma irradiation on degradation of nonmetallic materials for high temperature applications. 1 Managed by UT-Battelle for the U.S. Department of Energy Effects of neutron and gamma irradiation on degradation of nonmetallic materials for.
Failures in the basic materials used in nuclear power plants continue to be costly and insidious, despite increasing industry vigilance to catch failures before they degrade safety. For instance, the overall costs to the US industry from materials problems could amount to as much as $10 billion annually.
Moreover, estimates indicate that the cost of a pipe failure in a nuclear plant is. The kinetics of intermetallic growth in the bulk, along the surface and grain boundaries (GBs) was studied in the Cd-Ni, Cd-Cu and Cu-Sn systems. Bulk dynamic diffusion coefficients exceed by a few orders of magnitudes the tracer self-diffusion coefficients in homogeneous phases.
The reasons for this difference are discussed in terms of departure of growing intermetallics from Cited by: 1. irradiation to fluences 10 19 n/sm 2 local insoluble intermetallic system Al-Mg-Si-Fe phases are shattered and dissipate on the sample, becoming practically uniform.
Especially on raster pictures of elements Mg and Si. After irradiation fluence 10 19 n/ sm 2 the sizes of intermetallic system Al-Mg-Si-Fe phases become not more than 0, 5 -2mkm.
Nitrogen doped 4H-SiC epitaxial layers grown by hot-wall chemical vapor deposition were investigated by Deep Level Transient Spectroscopy after irradiation with 6 MeV electrons at room temperature. This study is focusing on the influence of nitrogen doping and C/Si ratio on the behaviour of the Z1,2 and EH6,7 levels which occur in already as-grown material but are Author: Ioana Pintilie, K.
Irmscher, Ulrike Grossner, Bengt Gunnar Svensson, Bernd Thomas. Electron irradiation damage and the recovery in a Zr-based bulk amorphous alloy Zr55Cu30Al10Ni5 K Sugita 1, M Matsumoto, M Mizuno1,2, H Araki1,2, Y Shirai1,2 1Department of Materials Science and Engineering, Graduate School of Engineering, Osaka University, Yamada-oka, Suita, OsakaJapan.
for the irradiation-induced amorphization of Ni 3 Ta. Fig. 3 shows the Vickers hardness as a function of ion fluence. The hardness of Ni 3 Ta intermetallic compound is increased by the irradiation-induced lattice structure transformation.
This change for Ni 3 Ta is similar to that for Ni 3 Nb 4). This result can be explained as the.TEM was used to observe the crystallographic defect structures caused by irradiation damage, including dislocation loops and voids.
APT was used to study the precipitation of Cr-rich α' phase under irradiation-enhanced diffusion process. EBSD is used to examine the grain size distribution and possible grain growth.EFFECT OF NEUTRON IRRADIATION AT K ON GUINIER-PRESTON ZONE FORMATION IN ALUMINUM-ZINC ALLOYS [J.A., et al Horak] on Author: Horak, J.A., et al.