Ensuring of the design value of fuel burnup in hightemperature gascooled reactor with operability graphite

7/14/2013 2013 - #02 Physics and technology of nuclear reactors

Nesterov V.N.

https://doi.org/10.26583/npe.2013.2.16

This paper describes a method of determining compliance of exhausted graphite’s resource of fuel blocks in high temperature gascooled reactor with fuel burnup. Obtained axial distribution of local values of exhausted resource of graphite of fuel blocks. It is shown that for ensuring of the design value for burnup fuel with operability graphite fuel blocks is need to reduce the average mixed temperature of helium coolant leaving the reactor core and reduce the time between congestion nuclear fuel.

Link for citing the article: Nesterov V.N. Ensuring of the design value of fuel burnup in hightemperature gascooled reactor with operability graphite. Izvestiya vuzov. Yadernaya Energetika. 2013, no. 2, pp. 133-142; DOI: https://doi.org/10.26583/npe.2013.2.16 (in Russian).