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Zhdanov, V.S.; Ivanov, M.V.
Abstracts of reports of the scientific-technical seminar on pulsed research reactors1997
Abstracts of reports of the scientific-technical seminar on pulsed research reactors1997
AbstractAbstract
[en] Determination methods of thermal and physical characteristics of the material irradiated in experimental channel of IGR reactor to study reliability of the reactor-NRE-prototype unite subjected to loads and neutron flux that is close, according to intensity, to the real conditions of testing, were developed
Original Title
Vnutrireaktornoe issledovanie teplofizicheskikh kharakteristik materialov YaRD
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Source
Donbaev, K.M.; Perepelkin, I.G. (eds.); Institut Atomnoj Ehnergii Natsional'nogo Yadernogo Tsentra Respubliki Kazakhstan (Kazakhstan); 48 p; 1997; p. 30-31; Scientific-technical seminar on pulsed research reactors; Nauchno-tekhnicheskij seminar Impul'snye issledovatel'skie reaktory; Kurchatov (Kazakhstan); 9-11 Jun 1998
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Miscellaneous
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