Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

被引：13
|
作者：
Ezell, N. Dianne Bull [1 ]
Raiman, Stephen S. [1 ]
Kurley, J. Matt [1 ]
McDuffee, Joel [1 ]
机构：
[1] Oak Ridge Natl Lab, 1 Bethel Valley Rd, Oak Ridge, TN 37830 USA
来源：
NUCLEAR ENGINEERING AND TECHNOLOGY | 2021年 / 53卷 / 03期
关键词：
Corrosion; High-temperature experiment; Molten Salt Reactor; Irradiation; CORROSION; RADIOLYSIS; FLUORIDE;
D O I：
10.1016/j.net.2020.07.042
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：
Capsules containing NaCl-MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation-corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts.
引用
收藏
页码：920 / 926
页数：7
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