Alloys compatibility in molten salt fluorides: Kurchatov Institute related experience

被引：54

作者：

Ignatiev, Victor ^{[1
]}

Surenkov, Alexandr ^{[1
]}

机构：

[1] IV Kurchatov Atom Energy Inst, Natl Res Ctr, Moscow 123182, Russia

来源：

JOURNAL OF NUCLEAR MATERIALS | 2013年 / 441卷 / 1-3期

关键词：

Compendex;

D O I：

10.1016/j.jnucmat.2013.05.007

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

In the last several years, there has been an increased interest in the use of high-temperature molten salt fluorides in nuclear power systems. For all molten salt reactor designs, materials selection is a very important issue. This paper summarizes results, which led to selection of materials for molten salt reactors in Russia. Operating experience with corrosion thermal convection loops has demonstrated good capability of the "nickel-molybdenum alloys + fluoride salt fueled by UF4 and PuF3 + cover gas" system up to 750 degrees C. A brief description is given of the container material work in progress. Tellurium corrosion of Ni-based alloys in stressed and unloaded conditions studies was also tested in different molten salt mixtures at temperatures up to 700-750 degrees C, also with measurement of the redox potential. HN80MTY alloy with 1% added Al is the most resistant to tellurium intergranular cracking of Ni-base alloys under study. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：592 / 603

页数：12

共 27 条

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