A radioactive tracer dilution method to determine the mass of molten salt

被引:0
作者
Lei Cao
Josh Jarrell
Susan White
Kevin Herminghuysen
Andrew Kauffman
Douglas E. Hardtmayer
Jeff Sanders
Shelly Li
机构
[1] The Ohio State University,Nuclear Engineering Program, Department of Mechanical and Aerospace Engineering
[2] The Ohio State University,Nuclear Reactor Laboratory, College of Engineering
[3] Idaho National Laboratory,Fuel Cycle Science and Technology
来源
Journal of Radioanalytical and Nuclear Chemistry | 2017年 / 314卷
关键词
Radioactive tracer; Molten salt; Mass determination; Volume; Pyro-processing; Molten salt reactor;
D O I
暂无
中图分类号
学科分类号
摘要
A new technique for molten salt mass determination, termed radioactive tracer dilution, that uses 22Na as a tracer was validated at bench scale. It has been a challenging problem to determine the mass of molten salt in irregularly shaped containers, where a highly radioactive, high-temperature molten salt was used to process nuclear spent/used fuel during electrochemical recycling (pyro-processing) or for coolant/fuel salt from molten salt reactors. A radioactive source with known activity is dissolved into the salt. After a complete mixture, a small amount of the salt is sampled and measured in terms of its mass and radioactivity. By finding the ratio of the mass to radioactivity, the unknown salt mass in the original container can be precisely determined.
引用
收藏
页码:387 / 393
页数:6
相关论文
共 4 条
[1]  
Vaden DE(2008)Fuel conditioning facility electrorefiner model predictions versus measurements Sep Sci Technol 43 9-10
[2]  
Vaden DE(2006)Fuel conditioning facility electrorefiner process model Sep Sci Technol 41 10-32
[3]  
Mariani RD(2010)Modeled salt density for nuclear material estimation in the treatment of spent nuclear fuel J Nucl Mater 404 25-undefined
[4]  
Vaden DE(undefined)undefined undefined undefined undefined-undefined