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Strain-Path Change Tests and Physically Based Polycrystalline Modeling of the Behavior of Recrystallized Zirconium Alloys

• Authors : Onimus, Fabien; Bono, Matthew; Garnier, Jerome ...

Subjects: zirconium alloys mechanical behavior strain hardening kinematic hardening anisotropy biaxiality; zirconium alloys; mechanical behavior

• Source: Zirconium in the Nuclear Industry: 18th International Symposium ; https://hal-emse.ccsd.cnrs.fr/emse-04064646 ; Zirconium in the Nuclear

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Deformation mechanisms of zirconium alloys after irradiation studied by dislocation dynamics simulations and in situ straining experiments in TEM

• Authors : Onimus, Fabien; Dupuy, Laurent; Gaumé, Marine ...

Subjects: [CHIM.MATE]Chemical Sciences/Material chemistry; [PHYS.COND.CM-MS]Physics [physics]/Condensed Matter [cond-mat]/Materials Science [cond-mat.mtrl-sci]

• Source: Zirconium in the Nuclear Industry: 19th International Symposium ; https://hal.science/hal-03380264 ; Zirconium in the Nuclear Industry:

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Radiation Effects in Zirconium Alloys

• Authors : Onimus, Fabien; Doriot, Sylvie; Béchade, J.-L. ...

Subjects: Anisotropy Creep Damage Dislocation Hardening Irradiation Irradiation growth Irradiation loops Mechanical properties; [SPI.MAT]Engineering Sciences [physics]/Materials

• Source: Comprehensive Nuclear Materials ; https://hal-emse.ccsd.cnrs.fr/emse-04064758 ; R. Konings, R. Stoller. Comprehensive Nuclear Materials, 3, Elsevier, pp.1-56, 2020, 9780081028650.

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Impact of Hydrogen Pick-Up and Applied Stress on C-Component Loops: Toward a Better Understanding of the Radiation Induced Growth of Recrystallized Zirconium Alloys

• Authors : Tournadre, L.; Onimus, F.; Béchade, J.-L. ...

Subjects: [SPI.MAT]Engineering Sciences [physics]/Materials

• Source: Zirconium in the Nuclear Industry: 17th Volume ; https://hal-emse.ccsd.cnrs.fr/emse-04064696 ; Zirconium in the Nuclear Industry: 17th

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volved the use of ultra-clean ic e particles, having a uniform grain size, for clean-ing the surface and grooves of ferrite block (Tomoji [4]). An ice blasting device utilizing stored particle s was suggested by Harima [5]. Vissisouk [6] proposed to use ice particles near melting temperature for surface decoating. Mesher [7] de-velope d a nozzle for enhancement of the surface cleaning by ice blasting. Shinichi [8] suggested an inexpensive cleaning of various surfaces by mixing ice particles, cold water and air. Niechial [9] proposed an ice blasting cleaning system contain-ing an ice crusher, a separator and a blasting gun. Settles [10] suggested produc-ing ice particles of a size range below 100 urn within the apparatus just prior to the nozzle. Although the potential use of ice blasting has been suggested by a number of inventors, the practical use is much more limited. Herb and Vissisouk [11] re-ported precision cleaning of zirconium alloys in the course of production of bi-metallic tubing by ice pellets. It was shown that ice blasting improved the quality of bimetal. The use of air-ice blasting for steel derusting was reported by Liu [12]. The following operational conditions were maintained: air pressure: 0.2-0.76 MPa; grain diameter: below 2.5 mm; ice temperature -50°C; traverse rate 90 mm/min; and standoff distanc e 50 mm. At these conditions the rate of derusting ranged from 290 mm/min at the air pressure of 0.2 MPa to 1110 mm /min at the

• Source: Surface Contamination and Cleaning ; page 146-147 ; ISBN 9780429087967

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Zirconium and Zirconium Alloys

• Source: Metallic Materials ; ISBN 9780824708788 9780203912423

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Irradiation creep in materials

• Authors : Onimus, Fabien; Jourdan, Thomas; Xu, Cheng ...

Subjects: creep; irradiation; dislocation

• Source: Comprehensive Nuclear Materials ; https://hal.science/hal-04065942 ; R. Konings; R. Stoller. Comprehensive Nuclear Materials, 1, Elsevier, pp.310-366, 2021, 978-0-08-102866-7.

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Semi-mechanistic approach for the kinetic evaluation of experiments on the oxidation of zirconium alloys

• Authors : Schanz, G.

Subjects: ddc:620; Engineering & allied operations; info:eu-repo/classification/ddc/620

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OVERAGING OF OUTOKUMPU CuCrZr AT 600 DEGREES C

• Authors : Singh, Bachu

• Source: Other Information: Fusion Materials: Semi-Annual Progress Report for Period Ending December 31, 2001, 31:118-122.

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Influence of Hydrogen Content on Axial Fracture Toughness Parameters of Zr-2.5Nb Pressure Tube Alloy in the Temperature Range of 306-573 K

• Authors : Singh, Ram Nivas; Ståhle, Per; Iyengar, Srinivasan

Subjects: Mechanical Engineering; Materials Engineering; Fracture toughness

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