Investigations of BOR-60 structural materials and prospects for further work

被引：2

作者：

Golovanov, VN ^{[1
]}

Shamardin, VK ^{[1
]}

Prokhorov, VI ^{[1
]}

Neustroev, VS ^{[1
]}

Kazakov, VA ^{[1
]}

Kobylyanskii, GP ^{[1
]}

Pecherin, AM ^{[1
]}

Povstyanko, AV ^{[1
]}

Bulanova, TM ^{[1
]}

Krasnoselov, VA ^{[1
]}

Fedoseev, AE ^{[1
]}

机构：

[1] Sci Res Inst Nucl Reactors, State Sci Ctr Russian Federat, Moscow, Russia

来源：

ATOMIC ENERGY | 2001年 / 91卷 / 05期

关键词：

Heat Treatment; Structural Material; Service Life; Irradiation Condition; Type Reactor;

D O I：

10.1023/A:1014222025196

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Since its startup in December in 1969, the BOR-60 reactor has been used effectively for irradiation of structural and fuel materials in a wide range of dose-temperature parameters. Analysis of the actual computational-experimental parameters (irradiation temperature, damage rates) shows that the irradiation conditions are highly reproducible and can be maintained accurately. The investigations made it possible to study phenomena which are important for building reactors using domestic structural materials and to choose the optimal composition and heat treatment of the materials. New directions are indicated for scientific-research work, for improving and increasing the service life of VVER type reactors, and for developing new-generation structural materials for fusion reactors being designed.

引用

页码：937 / 950

页数：14

共 10 条

[1]

GAMER F, 1994, J NUCL MATER, V1, P419

[2]

KAZAKOV V, 1999, DLEER0131327, P243

[3]

Neustroev V. S., 1997, Physics of Metals and Metallography, V83, P555

[4] Irradiation induced growth and microstructure evolution of Zr-1.2Sn-1Nb-0.4Fe under neutron irradiation to high doses [J].

Nikulina, AV ;

Shishov, VN ;

Peregud, MM ;

Tselischev, AV ;

Shamardin, VK ;

Kobylyansky, GP .

EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 :1045-1061

[5]

POVSTYANKO AV, 1994, 3 INT C REACT MAT EN, P231

[6]

SCHAMARDIN VK, 1999, J NUCL MATER, P271

[7] Mechanical properties and microstructure of advanced ferritic-martensitic steels used under high dose neutron irradiation [J].

Shamardin, VK ;

Golovanov, VN ;

Bulanova, TM ;

Povstianko, AV ;

Fedoseev, AE ;

Goncharenko, YD ;

Ostrovsky, ZE .

JOURNAL OF NUCLEAR MATERIALS, 1999, 271 :155-161

[8]

SHAMARDIN VK, 1990, RAD MAT ENG, V3, P49

[9]

Van Duysen J. C., 1993, ASTM STP, P747

[10]

Votinov S. N., 1987, IRRADIATED STAINLESS

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