... 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...

...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...

...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...

...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...

...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...

... 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...

... 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...

..., 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...

... 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...

...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...

...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...

...) 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...

...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...

... 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...

... 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...

...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...