Investigations of structural metals in BOR-60 and prospects of their development

被引：0

作者：

Golovanov, V.N. ^{[1
]}

Shamardin, V.K. ^{[1
]}

Prokhorov, V.I. ^{[1
]}

机构：

[1] GNTs RF - NIIAR, Dimitrovgrad, Russia

来源：

Atomnaya Energiya | 2001年 / 91卷 / 05期

关键词：

Composition - Fast reactors - Forecasting - Heat treatment - Irradiation - Optimization - Radiation effects - Stability - Stainless steel - Zirconium alloys;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

During almost thirty years the BOR-60 reactor is used for irradiation of structural metals and fuel materials in a wide range of dose and temperature parameters. It is noted that the irradiation conditions are reproduced with high accuracy and stability. The carried out researches permitted to study the domestic reactor materials and to determine their optimum compositions and heat treatments. Prospects of investigations of materials for the new generation of the WWER type reactors and the designed thermonuclear reactors are discussed.

引用

页码：389 / 400