USE OF LEAD-BISMUTH COOLANT IN NUCLEAR-REACTORS AND ACCELERATOR-DRIVEN SYSTEMS

Authors
GROMOV BF BELOMITCEV YS YEFIMOV EI LEONCHUK MP MARTINOV PN ORLOV YI PANKRATOV DV PASHKIN YG TOSHINSKY GI CHEKUNOV VV SHMATKO BA
Citation
Bf. Gromov et al., USE OF LEAD-BISMUTH COOLANT IN NUCLEAR-REACTORS AND ACCELERATOR-DRIVEN SYSTEMS, Nuclear Engineering and Design, 173(1-3), 1997, pp. 207-217
Citations number
27
Journal title
Nuclear Engineering and Design → ACNP
ISSN journal
00295493
Volume
173
Issue
1-3
Year of publication
1997
Pages
207 - 217
Database
ISI
SICI code
0029-5493(1997)173:1-3<207:UOLCIN>2.0.ZU;2-N
Abstract
Experience of using lead-bismuth coolant in reactors of Russian nuclea r submarines is briefly presented. The salient points of the concept p roviding the safety of reactor facilities cooled by a lead-bismuth eut ectic are covered. The key results of developments for use of a lead-b ismuth coolant in nuclear reactors and accelerator-driven systems are presented. (C) 1997 Elsevier Science S.A.