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)

Manylion Llyfryddiaeth
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]
Awdur Corfforaethol: Национальный исследовательский Томский политехнический университет
Awduron Eraill: Baybakov D., Naymushin A. G. Artem Georgievich, Nesterov V. N. Vladimir Nikolaevich, Savanuk S., Shamanin I. V. Igor Vladimirovich
Crynodeb: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
Iaith:Saesneg
Cyhoeddwyd: 2015
Cyfres:Nuclear Engineering and Fuel Cycles
Pynciau:
Mynediad Ar-lein:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.294
Fformat: Electronig Pennod Llyfr
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640325

Eitemau Tebyg