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

التفاصيل البيبلوغرافية
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]
مؤلف مشترك: Национальный исследовательский Томский политехнический университет
مؤلفون آخرون: 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
الملخص: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
اللغة:الإنجليزية
منشور في: 2015
سلاسل:Nuclear Engineering and Fuel Cycles
الموضوعات:
الوصول للمادة أونلاين:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.313
التنسيق: الكتروني فصل الكتاب
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640332
الوصف
الملخص: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