Reactor graphite

被引：11

作者：

Virgil'ev, YS ^{[1
]}

Kalyagina, IP ^{[1
]}

机构：

[1] Res Inst Struct Graphite Mat, Moscow, Russia

来源：

INORGANIC MATERIALS | 2003年 / 39卷 / Suppl 1期

关键词：

Radiation; Graphite; Inorganic Chemistry; Service Life; Irradiation Effect;

D O I：

10.1023/A:1024184802515

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The production and properties of Russian reactor graphites are described, and a criterion for their performance is proposed. The underlying trends in the irradiation behavior of graphite and the irradiation effects on its structure and properties are analyzed. A method is considered for predicting the radiation resistance of graphite. This method made it possible to substantiate the feasibility of using pitch and schistose cokes, readily available raw materials, in the production of reactor graphite. Criteria are proposed for the serviceability of graphite and graphite stacks in reactors and are used to analyze the performance of graphite stacks during the service life of reactors. Approaches to the disposal of graphite from decommissioned reactors are considered.

引用

页码：S46 / S58

页数：13

共 50 条

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