Open AccessEXPERIMENTAL STUDIES ON DEVELOPMENT OF THE METHOD FOR DETERMINING THE AMOUNT OF IMPURITATED GASES IN NUCLEAR FUEL
Author(s) -
Galina Vityuk,
Vladimir Vityuk,
Alexander Vurim,
R. Y. Kelcingazina,
B. Y. Bekmagambetova
Publication year - 2022
Publication title -
vestnik nâc rk
Language(s) - English
Resource type - Journals
eISSN - 1729-7885
pISSN - 1729-7516
DOI - 10.52676/1729-7885-2021-3-29-36
Subject(s) - ampoule , nuclear engineering , graphite , core (optical fiber) , correctness , materials science , gas pressure , nuclear reactor core , nuclear fuel , computer science , petroleum engineering , composite material , engineering , programming language
The article is devoted to an issue of estimating the impurity gas amount in nuclear fuel in the aspect of the distracting contribution from released gases to the total pressure inside ampoule of the device in the simulating a severe accident with core melting. The paper presents a method based on measuring the pressure and temperature of gas in a closed values of the fuel elements during the fuel melting. The correctness of the developed methodology is confirmed by the results of experiments on the melting of fuel in a pulsed graphite reactor IGR with the implementation of a controlled neutron pulse.