POWER-GENERATING UNIT WITH DUAL-LOOP SODIUM-COOLED FAST REACTOR AND DUAL-WALL STEAM GENERATOR

被引：3

作者：

Bagdasarov, Yu. E. ^{[1
]}

Kamaev, A. A. ^{[1
]}

机构：

[1] State Sci Ctr Russian Federat, Leipunskii Inst Phys & Power Engn, GNTs RF FEI, Obninsk, Russia

来源：

ATOMIC ENERGY | 2009年 / 107卷 / 03期

关键词：

Steam; Steam Generator; Water Tube; Sodium Bismuth; Main Circulation Pump;

D O I：

10.1007/s10512-010-9210-6

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：

Due to advances in the technology of liquid metals, the idea, advanced in the 1950s, of replacing the intermediate sodium loop in a fast reactor with sodium coolant in the first loop by an intermediate stationary heat-transferring medium between the sodium flows in the first loop and water-steam is being revived. The mass/size characteristics and safety of such steam generators are evaluated from the standpoint of water-steam getting into the first loop of the reactor. Intermediate media that could be used are analyzed. An example of the implementation of dual-loop schemes for sodium-cooled fast reactors is proposed for a 900 MW(e) power-generating unit.

引用

页码：155 / 161

页数：7

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