共 9 条
[1]
Orlov V. V.(1994)Lead-cooled reactor core, its characteristics and features ARS-94 International Topical Meeting on Advanced Reactor Safety 1 516-523
[2]
Sila-Novitsky A. G.(2001)Channel–circuit in the BOR-60 reactor for testing BREST reactor fuel 11th Conference of the Russian Nuclear Society 2 55-71
[3]
Smirnov V. S.(2002)Experience in solving questions concerning the lead coolant in the AKST autonomous channel in the BOR-60 reactor during the period of the prereactors tests and the first microruns Heat Transfer and Properties of Liquid Metals 1 226-228
[4]
Efimov V. N.(undefined)undefined undefined undefined undefined-undefined
[5]
Zhemkov I. Y.(undefined)undefined undefined undefined undefined-undefined
[6]
Korol'kov A. S.(undefined)undefined undefined undefined undefined-undefined
[7]
Ivanov K. D.(undefined)undefined undefined undefined undefined-undefined
[8]
Korotkov V. I.(undefined)undefined undefined undefined undefined-undefined
[9]
Martynov P. N.(undefined)undefined undefined undefined undefined-undefined