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1-16 of 16
Keywords: irradiation
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Journal Articles
Philippe Bossis, Caroline Raepsaet, Marc Tupin, Caroline Bisor-Melloul, Hicham Khodja, Martine Blat, Antoine Ambard, Alain Miquet, Damien Kaczorowski
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2012, 9(1): 1–17.
Published Online: December 23, 2011
... by Nuclear Reaction Analysis and the hydrogen pickup by gas extraction. It was observed that the stability of the corrosion behaviour of M5 is not affected by increased Li or elevated temperature conditions. The hydrogen pickup fraction of M5 is not modified by increased Li conditions or by irradiation...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2011, 8(1): 1–20.
Published Online: January 1, 2011
...P. Vizcaíno; A. V. Flores; P. B. Bozzano; A. D. Banchik; R. A. Versaci; R. O. Ríos The present work deals with two essential degradation mechanisms of zirconium alloys: Hydrogen behavior and microstructural transformations due to neutron irradiation. The studies were carried out by using samples...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. July 2010, 7(7): 1–22.
Published Online: July 1, 2010
...V. N. Shishov A review is given on the effect of neutron irradiation on the microstructure and properties of Zr–Nb and Zr–Nb–Fe (Sn,O) alloys. The in-reactor performance of Zr alloys is dependent on their composition and microstructure, and even small changes in the composition and processing lead...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. March 2008, 5(3): 1–14.
Published Online: March 1, 2008
...R. K. Nanstad; M. A. Sokolov; D. E. McCabe The Heavy-Section Steel Irradiation Program at Oak Ridge National Laboratory has evaluated a submerged-arc (SA) weld irradiated to a high level of embrittlement and a temper embrittled base metal that exhibits significant intergranular fracture relative...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2008, 5(1): 1–11.
Published Online: January 1, 2008
...I. A. Evdokimov; V. V. Likhanskii It is shown that irradiation of oxide film on the surface of zirconium alloy by fission fragments may promote the breakdown of oxide protective properties and lead to massive hydriding of zirconium in a steam-hydrogen environment far beyond the condition of “oxygen...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2008, 5(1): 1–9.
Published Online: January 1, 2008
... irradiation creep models are needed to predict the deformation behavior of the core components over the reactor life. It is important to know the creep behavior as a function of neutron flux in order to develop creep models over the range of operating conditions in the reactor core. At the edge of the reactor...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2008, 5(1): 1–8.
Published Online: January 1, 2008
... microstructure (texture, grain size, dislocation density, and phase or precipitate distribution) determines the basic physical properties of a given component, there are changes that occur during irradiation that can have a significant effect on these properties. Microstructures that illustrate specific features...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2008, 5(1): 1–11.
Published Online: January 1, 2008
..., and ⟨a⟩ or ⟨c+a⟩ slip on pyramidal planes, and twinning). This means that the yield strength (and ultimate tensile strength) for directions with a strong basal pole texture is higher than directions with a strong prism pole texture. Irradiation increases the yield stress on all slip planes due to the formation...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. April 2006, 3(4): 1–7.
Published Online: April 1, 2006
... is among the few potential refractory ceramic materials with necessary properties to be considered as matrix materials for a dispersed carbide fuel. The radiation response of ZrC to high dose and temperature is a critical research need. This work investigated the microstructure of ZrC irradiated with 1 MeV...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. January 2006, 3(1): 1–18.
Published Online: January 1, 2006
...V Dubinko; A Turkin; A Abyzov; M Griffiths We present a model of the homogeneous nucleation and growth of vacancy and interstitial loops in irradiated hcp metals, which allows one to find the size distribution function, the dose dependence of the mean parameters of the dislocation system...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. November 2005, 2(10): 1–17.
Published Online: November 1, 2005
...M Li; SJ Zinkle This paper addresses various deformation mechanisms of unirradiated and irradiated V-4Cr-4Ti in terms of Ashby-type deformation maps. Tensile tests were carried out in the temperature range of 950–1150°C at strain rates of 10 −3 , 10 −4 , and 10 −5 s −1 . In addition, published...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. October 2005, 2(9): 1–17.
Published Online: October 1, 2005
...) and the Heavy-Section Steel Irradiation Program of Oak Ridge National Laboratory (ORNL), groups of Charpy impact, tensile, and precracked Charpy specimens of the JRQ plate were irradiated by PSI to four different fast neutron fluences [from 0.39 to 5.0 × 10 23 n/m 2 (>1 MeV)] in a test reactor. Additional...
Journal Articles
Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
F Onimus, J-L Béchade, C Prioul, P Pilvin, I Monnet, S Doriot, B Verhaeghe, D Gilbon, L Robert, L Legras, J-P Mardon
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. September 2005, 2(8): 1–24.
Published Online: September 1, 2005
...F Onimus; J-L Béchade; C Prioul; P Pilvin; I Monnet; S Doriot; B Verhaeghe; D Gilbon; L Robert; L Legras; J-P Mardon TEM investigations have been performed on irradiated samples after deformation covering various testing conditions for different recrystallized Zr alloys. It is shown...
Journal Articles
VN Shishov, MM Peregud, AV Nikulina, YV Pimenov, GP Kobylyansky, AE Novoselov, ZE Ostrovsky, AV Obukhov
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. September 2005, 2(8): 1–18.
Published Online: September 1, 2005
... that have proved well in terms of irradiation-induced creep and growth, high strength characteristics, and corrosion. The difference between the alloy properties is determined by their states related to their compositions. The structure-phase state of the Zr-Nb and Zr-Nb-Fe-Sn systems has been studied after...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. July 2005, 2(7): 1–24.
Published Online: July 1, 2005
...S Doriot; D Gilbon; J-L Béchade; M-H Mathon; L Legras; J-P Mardon The present paper is focused on the microstructural stability of the Framatome-ANP M5™ (Zr-1%NbO) alloy. Thin foils were cut from M5 cladding tubes irradiated from 1 to 6 annual cycles in EDF PWRs, and examined by analytical...
Journal Articles
Journal:
Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. July 2005, 2(7): 1–21.
Published Online: July 1, 2005
... creep and the transition from thermal to irradiation creep with increasing neutron flux. 17 03 2004 28 12 2004 08 06 2005 zirconium irradiation thermal creep deformation strain fast neutron flux radiation damage point defects vacancy interstitial dislocation loops...