Use of lead-bismuth coolant in nuclear reactors and accelerator-driven systems

被引：153

作者：

Gromov, BF ^{[1
]}

Belomitcev, YS ^{[1
]}

Yefimov, EI ^{[1
]}

Leonchuk, MP ^{[1
]}

Martinov, PN ^{[1
]}

Orlov, YI ^{[1
]}

Pankratov, DV ^{[1
]}

Pashkin, YG ^{[1
]}

Toshinsky, GI ^{[1
]}

Chekunov, VV ^{[1
]}

Shmatko, BA ^{[1
]}

机构：

[1] RDB GIDROPRESS,PODOLSK,MOSCOW REGION,RUSSIA

来源：

NUCLEAR ENGINEERING AND DESIGN | 1997年 / 173卷 / 1-3期

关键词：

D O I：

10.1016/S0029-5493(97)00110-6

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Experience of using lead-bismuth coolant in reactors of Russian nuclear submarines is briefly presented. The salient points of the concept providing the safety of reactor facilities cooled by a lead-bismuth eutectic are covered. The key results of developments for use of a lead-bismuth coolant in nuclear reactors and accelerator-driven systems are presented. (C) 1997 Elsevier Science S.A.

引用

页码：207 / 217

页数：11