... Zirconium oxide formed in high-temperature water conditions is highly heterogeneous in nature, with, for instance, the presence of a high density of grain boundaries and nanopores, secondary-phase precipitates, and microchemical segregations. Irradiation exacerbates these heterogeneities...

... During operation, structural components made of zirconium alloys are subject to neutron irradiation, which leads to the displacement of zirconium atoms from their lattice sites, the production of self-interstitials and vacancies, and eventually dislocation loops. This process can lead...

... alloys, including M5 Framatome and Q12, and their microstructural evolution after neutron irradiation, in the same campaign, as fuel rods in a PWR up to high fluence. Previous studies have detailed microstructural changes of zirconium alloys under irradiation and have underlined the influence...

... in the irradiated materials. Additionally, the matrix concentrations of solute elements in (nonirradiated) Zircaloy-2 were investigated for a series of samples subjected to α annealing at 770°C followed by cooling at different rates. From these measurements, the solubilities at 770°C were estimated to be around 65...

... This paper reviews the prediction methods used in France for the assessment of irradiation and thermal aging effects. The irradiation embrittlement trend correlation (ETC) was revised in 2007, and a further revision depends on the significant surveillance database expansion that will occur over...

... 15Kh2MFA-type steel forgings were irradiated in an accelerated surveillance position of a power reactor, up to about 1 × 10 21 n/cm 2 , E > 1 MeV with medium flux. This steel is a Cr-Mo-V-type low-copper reactor pressure vessel material. 15Kh2MFA was microstructurally tested as received...

... with two accelerators: a 2-MV Van de Graaff/tandem “Aramis” and a 190-kV ion implanter “Irma.” In the first part of this paper, after a brief description of both facilities, the performances allowed in terms of suppress the irradiation configuration will be presented and discussed. Then, we will illustrate...

... reactions. As a result of the neutron absorption they become highly radioactive, which can impede maintenance. When nuclear reactors were first designed and built the effect of neutron irradiation on the core materials after many years of operation was largely unknown. Accelerated tests were therefore...

... Neutron irradiation often introduces severe changes in the mechanical properties of austenitic and martensitic steels (e.g., reduction of elongation below 400°C). This affects the mechanical responses of the reactor components. A large amount of hot cell work, however, is required in order...

... 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...

... 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...

... 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...

... 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 starvation.” Massive hydriding...

... The diametral expansion, elongation, and sag rates of Zr-2.5Nb pressure tubes in CANDU® (CANada Deuterium Uranium) nuclear reactors are important properties that limit their useful life and the maximum power level for reactor operation. As a result irradiation creep models are needed to predict...

... 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 of dislocation loops...

... The International Atomic Energy Agency has sponsored a number of studies involving a specific plate of A533 grade B class 1 steel designated heat JRQ. In this cooperative study between the Paul Scherrer Institute (PSI) and the Heavy-Section Steel Irradiation Program of Oak Ridge National...

... 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 tensile data...

... 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 Kr ions to doses of 10 and 30 dpa...

... TEM investigations have been performed on irradiated samples after deformation covering various testing conditions for different recrystallized Zr alloys. It is shown that for transverse tensile tests and internal pressure tests performed at 350°C, only basal channels are observed for strain...

... 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, and to describe effects due to temperature...