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)

Bibliografiske detaljer
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]
Institution som forfatter: Томский политехнический университет
Andre forfattere: Baybakov D., Naymushin A. G. Artem Georgievich, Nesterov V. N. Vladimir Nikolaevich, Savanuk S., Shamanin I. V. Igor Vladimirovich
Summary: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
Sprog:engelsk
Udgivet: 2015
Serier:Nuclear Engineering and Fuel Cycles
Fag:
Online adgang:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.294
Format: Electronisk Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640325
Beskrivelse
Summary: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