2024/03/05 by V. V. Ryazanov, Ryazanov, V. V.
Engineering · Materials Science · #FOS: Physical sciences #Graphite, nuclear technology, radiation studies #Instrumentation and Detectors (physics.ins-det) #Nuclear Materials and Properties #Nuclear reactor physics and engineering
paper · pdf · doi:10.48550/arxiv.2403.02675
openalex publication_date 2024/03/05 · openalex created_date 2025/10/10 · openalex updated_date 2026/07/28
A simple and rapid method is proposed for assessing the reduction in the lifetime of steel walls of the reactor vessel under neutron irradiation. The method is based on modeling the number of radiation defects by the behavior of a general time-dependent random process of death and birth and queuing theory. Necessary data for assessments: the estimated operating time of the reactor (in years), the actual operating time of the reactor, the accumulated fluence depending on time, the temperature on the walls of the reactor vessel, the neutron absorption cross section of the steel of the reactor walls, the energy of fast neutrons striking the walls. The main problem: getting this accurate data.