Heat removal verification tests using concrete casks under normal condition

被引：25

作者：

Takeda, Hirofumi ^{[1
]}

Wataru, Masunii ^{[1
]}

Shirai, Koji ^{[1
]}

Saegusa, Toshiari ^{[1
]}

机构：

[1] Cent Res Inst Elect Power Ind, Civil Engn Res Lab, Nucl Fuel Cycle Backend Res Ctr, Chiba 2701194, Japan

来源：

NUCLEAR ENGINEERING AND DESIGN | 2008年 / 238卷 / 05期

关键词：

D O I：

10.1016/j.nucengdes.2007.03.034

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：

Heat removal tests using two types of full-scale concrete casks were conducted. This paper describes the results under a normal condition of spent fuel storage. In the tests, data on heat removal performance and integrity of cask components were obtained for different storage periods. The change of decay heat of spent fuel was simulated using electric heaters. Reinforced concrete cask (RC cask) and concrete filled steel cask (CFS cask) were the specimen casks. Decay heat at the initial period of storage 60 years of storage, the middle period (20 years of storage), and the final period (40 years of storage) correspond to 22.6 kW, 16 kW and 10 kW, respectively. Quantitative temperature data of the cask components were obtained as compared with their limit temperature. In addition, heat balance data requested for heat removal analyses were obtained. (C) 2007 Elsevier B.V. All rights reserved.

引用

页码：1196 / 1205

页数：10