Characteristics of the thermal desorption of helium from the model alloys Kh16N15 and Kh13

Thermal desorption spectrometry is used to study the characteristic behavior of helium in the new model bcc and fcc alloys Fe-13Cr and Fe-16Cr-15Ni, which are the basis of structural reactor steels, with the substitution elements Mo, W, Nb, Ta, V, and Ti and carbon. It is found that the gas-release spectra of bcc alloys are more complicated. The activation energy of gas release is calculated. It is shown that the alloying elements do not have a unique effect on the mechanisms of helium release from bcc and fcc alloys. The data obtained are discussed from the standpoint of the formation and thermal stability of different helium—vacancy complexes and the effect of doping by a change of the diffusion mechanisms on the growth and migration of bubbles. __________ Translated from Atomnaya énergiya, Vol. 104, No. 1, pp. 13–17, January, 2008.     

Radiation damage in helium-implanted 0Kh16N15M3B steel

National Nuclear Center of the Kazakhstan Republic, Nuclear Physics Institute. Translated from Atomnaya Énergiya, Vol. 74, No. 5, pp. 444–446, May, 1993.     

Hydrogen permeability in Kh18N10T stainless steel from plasma glow-discharge

Conclusions In the entire temperature range under consideration (520–1000°K), the radiation-induced desorption rate is higher than the thermal desorption rate.In the temperature range below 700°K, the magnitude of hydrogen permeability is determined by the radiation-induced desorption rate that depends on temperature according to the equationIn the 700–1000°K range this rate is independent of temperature, and is equal to 7.10^–3 cm/sec.Above 1000°K, the rates of the radiation-induced desorption, thermal desorption, and diffusional discharge are comparable, and the exponential temperature dependence of flux would be disrupted.Translated from Atomnaya Énergiya, Vol. 59, No. 4, pp. 269–273, October, 1985.     

The micro structural study of 15Kh2MFA and 15Kh2NMFA reactor pressure vessel steels using positron-annihilation spectroscopy, mössbauer spectroscopy and transmission electron microscopy

The micro structure of the non-irradiated low-alloyed steels (15Kh2MFA and 15Kh2NMFA) was studied using different spectroscopic methods as the positron annihilation lifetime and Doppler broadening techniques, the Mössbauer spectroscopy, and the Integral low-energy electron Mössbauer spectroscopy as well as the Transmission electron microscopy. Differences in the microstructural parameters of these types of RPV steels are well detectable using all methods. It was confirmed that the heat-affected zone of these steels is the most sensitive place for thermal embrittlement in the reactor. Positron-annihilation lifetime measurements on the successive annealed specimens (XTA, YTA), which simulated the heat-affected zone, showed the rapid increase in the vacancy-type defects formation in the temperature region 525–600°C. Therefore these specimens were studied using Transmission electron microscopy in more detail.     

Microstructure of the Kh18N10T steel irradiated in a BOR-60 reactor

Khar'kov Physical-Technological Institute (KhFTI). V. I. Lenin Scientific-Research Institute of Nuclear Reactors (NIIAR). Translated from Atomnaya Énergiya, Vol. 70, No. 3, pp. 159–163, March, 1991.