Materials science research for sodium cooled fast reactors

被引：14
|
作者：
Raj, Baldev [1 ]
机构：
[1] Indira Gandhi Ctr Atom Res, Kalpakkam 603102, Tamil Nadu, India
来源：
BULLETIN OF MATERIALS SCIENCE | 2009年 / 32卷 / 03期
关键词：
Nuclear energy; fast breeder reactors; materials science; stainless steels; sodium; THRESHOLD OXYGEN LEVELS; BREEDER TEST REACTOR; O SYSTEM; BEHAVIOR; STEEL; ELECTROLYTE; SIMULATION; COOLANT; FUEL;
D O I：
10.1007/s12034-009-0041-9
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The paper gives an insight into basic as well as applied research being carried out at the Indira Gandhi Centre for Atomic Research for the development of advanced materials for sodium cooled fast reactors towards extending the life of reactors to nearly 100 years and the burnup of fuel to 2,00,000 MWd/t with an objective of providing fast reactor electricity at an affordable and competitive price.
引用
收藏
页码：271 / 283
页数：13
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