Hydride Rim Formation in E110 Zirconium Alloy during Gas-Phase Hydrogenation

Abstract

The work is devoted to the study of the laws of the formation of a hydride rim in E110 zirconium alloy claddings during gas-phase hydrogenation. The problem of hydrogen penetration and accumulation and the subsequent formation of hydrides in the volume of zirconium cladding tubes of water-cooled power reactors remain relevant. The formation of brittle hydrides in a zirconium matrix firstly, leads to a significant change in the mechanical properties, and secondly, can cause the destruction of the claddings by the mechanism of delayed hydride cracking. The degree of the hydride’s effect on the mechanical properties of zirconium cladding is mainly determined by the features of the hydride’s distribution and orientation. The problem of hydride rim formation in zirconium alloys with niobium is quite new and poorly studied. Therefore, the study of hydride rim formation in Russian zirconium alloy is important and necessary for predicting the behavior of claddings during the formation of the hydride rim.

Improvement properties of protective coatings on zirconium alloys and austenitic stainless steels by pre-treatment with high-intense pulsed ion beams

“…To simulate radiation damage, the samples were irradiated on an ESG-2.5 accelerator with a proton beam with an energy of 400 keV and a current density j = 0.667 μA/cm 2 to achieve a fluence Ф = 2.25•10 16 proton/cm 2 . To simulate the process of hydrogen accumulation in the coating, hydrogen saturation was carried out on an automated complex Gas reaction controller in the SOAK mode [4], in which the samples are kept at a 2 atm pressure and at 360 °C temperature for 80 min. This mode provides the hydrogen concentration in the E110 alloy, close to the hydrogen concentration during the operation of the fuel element (5 years) (200-300 ppm) in water cooled reactors.…”

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

“…However, zirconium alloys readily absorb hydrogen through oxidation reactions with cooling water [1]. The solubility of hydrogen in zirconium alloys is relatively low, approximately 80 ppm at 300 • C and 200 ppm at 400 • C. Consequently, exceeding the solubility limit leads to the precipitation of brittle zirconium hydride [2]. The formation of zirconium hydride not only diminishes the mechanical properties but also influences the corrosion behavior of zirconium alloys [3][4][5][6].…”