Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors

Podrobná bibliografie
Parent link:Advanced Materials Research : Radiation and nuclear techniques in material science: Scientific Journal
Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014).— 2015.— [P. 313-316]
Korporativní autor: Национальный исследовательский Томский политехнический университет
Další autoři: Baybakov D. F., Golovathkiy A. V. Aleksey Vasilievich, Naymushin A. G. Artem Georgievich, Nesterov V. N. Vladimir Nikolaevich, Savanyuk S. N., Shamanin I. V. Igor Vladimirovich
Shrnutí:Title screen
This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges.
Режим доступа: по договору с организацией-держателем ресурса
Vydáno: 2015
Edice:Nuclear Engineering and Fuel Cycles
Témata:
On-line přístup:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.313
Médium: Elektronický zdroj Kapitola
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640332
Popis
Shrnutí:Title screen
This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.4028/www.scientific.net/AMR.1084.313