The long-term performance of concrete in nuclear applications

被引：0

作者：

Fillmore, Denzel L. ^{[1
]}

Winston, Philip L. ^{[1
]}

Morton, Sheryl L. ^{[1
]}

Hoffman, Cecelia R. ^{[1
]}

Van Ausdeln, Leo A. ^{[1
]}

Saegusa, Toshiari ^{[1
]}

Shirai, Koji ^{[1
]}

Hattori, Takatoshi ^{[1
]}

Sasahara, Akihiro ^{[1
]}

机构：

[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA

来源：

Proceedings of the ASME Pressure Vessels and Piping Conference 2005, Vol 7 | 2005年 / 7卷

关键词：

concrete; nuclear applications; spent nuclear fuel; VSC-17; storage;

D O I：

暂无

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

The Idaho National Laboratory investigated long-term concrete performance for nuclear applications. Scientists searched the open literature for information on the effects of heat and radiation. They also examined the concrete shield of the Pacific Sierra Nuclear Ventilated Storage Cask (VSC-17) for concrete deterioration and loss of shieldinf. The literature search revealed that low doses, < 10(9) n/cm(2) or < 10(11) Rad gamma, of radiation over periods less than 50 years do not appear to significantly affect concrete. Exposure over 100 years was not studied. The effects of higher doses of radiation are not as clear. Generally, the threshold of degradation is 95 degrees C, and degradation increases with increasing temperature and time. In 15 years of VSC-17 use, there is no apparent effect from environment, radiation, or temperature that has adversely affected the shielding or structural functions, although there has been some minor cracking of the concrete.

引用

页码：639 / 648

页数：10