期刊
ANNALS OF NUCLEAR ENERGY
卷 146, 期 -, 页码 -出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2020.107608
关键词
Molten salt; MSR; AHTR; Fluoride; Chloride; Thermal conductivity; Nuclear reactor; Uranium; Thorium; Thermophys cal property; Density; Viscosity; Specific heat capacity; Electrical conductivity; Uncertainty; Error
资金
- DOE Office of Nuclear Energy's Nuclear Energy University Program (NEUP) [DE-NE0008870]
- Nuclear Regulatory Commission (NRC) [31310019M0006]
Recent investigation into designs of molten salt reactors (MSR) requires accurate data of candidate salts. Review of the literature shows lacking thermophysical (TP) property data for coolants and fuel-bearing salts of Advanced High Temperature Reactors (AHTR). Measurement uncertainties of current data are even more deficient, and this affects ongoing research where MSR modeling and testing are being performed. Melting temperature, viscosity, density, specific heat capacity, and thermal and electrical conductivity measurements are often not arranged together or discussed in great detail, especially for fuel-bearing salts. Raw data from key findings spanning over 70 years for LiF, LiF-BeF2, LiF-NaF-KF, KCl-MgCl2, KF-ZrF4, and NaF-KF-MgF2 have been organized and presented here. Brief description of methods used to obtain these results, in addition to the TP data of some of these salts as fuel carriers, has also been discussed. Thermal conductivity data are particularly weak due to older, high-error measurement techniques. More recent measurement systems to evaluate salt thermal conductivity show promise for obtaining consistent absolute values. This paper concludes that measurement systems such as transient hot-wire method, forced Rayleigh scattering, and laser flash analysis provide the most promise to fill these data gaps and reduce current uncertainty in thermal conductivity measurements of both fueled and un-fueled molten salts. (C) 2020 Elsevier Ltd. All rights reserved.
作者
我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。
推荐
暂无数据