Thermohydraulic Calculation of VVER and SCWR Reactor Channels; Atomic Energy; Vol. 131, iss. 3

Bibliographic Details
Parent link:	Atomic Energy Vol. 131, iss. 3.— 2022.— [P. 140-143]
Main Author:	Korotkikh A. G. Aleksandr Gennadievich
Corporate Author:	Национальный исследовательский Томский политехнический университет Инженерная школа энергетики Научно-образовательный центр И. Н. Бутакова (НОЦ И. Н. Бутакова)
Other Authors:	Parimala R. F.. C. Rangan Fidel Castro
Summary:	Title screen The results of a comparative thermohydraulic calculation of the core channels of two types of nuclear reactors – VVER and VVER-SKD, differing in the coolant parameters at the inlet to the core channel – are presented. It was established that at the identical thermal power the maximum temperature at the center of a VVER-SKD fuel element is lower than that of a VVER fuel element. Режим доступа: по договору с организацией-держателем ресурса
Language:	English
Published:	2022
Subjects:	труды учёных ТПУ электронный ресурс
Online Access:	https://doi.org/10.1007/s10512-022-00855-7
Format:	Electronic Book Chapter
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=668472

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