Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor
Titel:
Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor
Auteur:
Kordyukov, A. G. Leonov, V. N. Pikalov, A. A. Sila-Novitskii, A. G. Filin, A. I. Brovko, V. V. Efimov, V. N. Korol'kov, A. S. Stynda, Yu. E. Yurchenko, A. D. Kostyukov, Yu. A. Rogozkin, B. D. Ryzhov, A. A. Ivanov, K. D. Martynov, P. N. Orlov, Yu. I. Pevchikh, Yu. M. Troyanov, V. M.
Verschenen in:
Atomic energy
Paginering:
Jaargang 97 (2004) nr. 2 pagina's 564-570
Jaar:
2004
Inhoud:
Uitgever:
Kluwer Academic Publishers-Plenum Publishers, New York