Abstract
This paper presents experimental results concerning the influence of pile irradiation upon the hydrogen penetration parameters in 07X16H6 martensite‐austenite steel, as well as simultaneous influence of hydrogen and pile irradiation upon the hydrogen gas release, sorption capacity and effective masstransfer coefficients of hydrogen in RGT and PGN graphite materials. To obtain the hydrogen penetration parameters in steel during the pile “PA” irradiation with the flux density 5×1016 n/cm2 s, the hydrogen permeability method was used with masspectrometer gas transfer quantity registration. Investigations of gas release, gas retention and, effective masstransfer parameters of hydrogen in graphite materials were carried out using the methods of thermostimulated gas release in the isochronous and linear heating regimes. Samples were exposed to irradiation in the IVG.1M nuclear reactor with total fluence 1.5×1022 n/m2. The pile irradiation was obtained to stimulate the process of hydrogen permeation in 07X16H6 steel and leads to hydrogen retention in graphite. The substantial difference was observed in the gas release of the graphite samples being saturated with hydrogen “in situ” reactor irradiation and the samples that were previously irradiated and then saturated with hydrogen.