Determining Reactor Graphite Lifespan from Thermal Properties Degradation; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)

Dettagli Bibliografici
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. 294-297]
Ente Autore: Национальный исследовательский Томский политехнический университет
Altri autori: Baybakov D., Naymushin A. G. Artem Georgievich, Nesterov V. N. Vladimir Nikolaevich, Savanuk S., Shamanin I. V. Igor Vladimirovich
Riassunto:Title screen
This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal properties’ degradation and the changes in the form of structural elements. Besides, some features associated with the differences in the neutron flux spectrum and differences in characteristics of gamma radiation field in the fuel and in the channels of control and protection system (CPS) were all taken into account.
Режим доступа: по договору с организацией-держателем ресурса
Lingua:inglese
Pubblicazione: 2015
Serie:Nuclear Engineering and Fuel Cycles
Soggetti:
Accesso online:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.294
Natura: Elettronico Capitolo di libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640325
Descrizione
Riassunto:Title screen
This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal properties’ degradation and the changes in the form of structural elements. Besides, some features associated with the differences in the neutron flux spectrum and differences in characteristics of gamma radiation field in the fuel and in the channels of control and protection system (CPS) were all taken into account.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.4028/www.scientific.net/AMR.1084.294