Hot Isostatic Pressing Temperature Effect on Chromium-Zirconium Copper Alloy Structure and Properties

被引：0

作者：

Suvorova, A. A. ^{[1
]}

Korostelev, A. B. ^{[2
]}

Goslavskii, O. V. ^{[2
]}

机构：

[1] State Corp Rosatom, JSC Sci & Innovat, Moscow, Russia

[2] Dollezhal Res & Dev Inst Power Engn NIKIET, Moscow, Russia

来源：

ATOMIC ENERGY | 2021年 / 130卷 / 05期

关键词：

CR-ZR ALLOY; THERMAL CYCLE;

D O I：

10.1007/s10512-021-00810-y

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：

Hot isostatic pressing, one of the most promising ways of obtaining high-quality joining of metallic materials, is to be used in the manufacture of permanent joints for the structural elements of fusion reactor installations. However, it can significantly affect the structure and properties of a material. The effect of hot isostatic pressing was investigated on samples of a chromium-zirconium copper alloy selected for the manufacture of individual in-chamber structural elements of fusion reactors. This alloy is preferred because of its enhanced electrical and thermal conduction as well as high strength. The present work is concerned with the effect of temperature, simulating hot isostatic pressing, on the structure and properties of the alloy. The optimal hot isostatic pressing temperature in combination with subsequent heat treatment which afford the necessary physical and mechanical properties of the chromium-zirconium copper alloy was determined.

引用

页码：285 / 289

页数：5

共 9 条

[1] The precipitation behaviour of ITER-grade Cu-Cr-Zr alloy after simulating the thermal cycle of hot isostatic pressing [J].

Holzwarth, U ;

Stamm, H .

JOURNAL OF NUCLEAR MATERIALS, 2000, 279 (01) :31-45

[2] On the recovery of the physical and mechanical properties of a CuCrZr alloy subjected to heat treatments simulating the thermal cycle of hot isostatic pressing [J].

Holzwarth, U ;

Pisoni, M ;

Scholz, R ;

Stamm, H ;

Volcan, A .

JOURNAL OF NUCLEAR MATERIALS, 2000, 279 (01) :19-30

[3] Evaluation of hot isostatic pressing for joining of fusion reactor structural components [J].

Ivanov, AD ;

Sato, S ;

Le Marois, G .

JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) :35-42

[4] Specification of properties and design allowables for copper alloys used in HHF components of ITER [J].

Kalinin, GM ;

Fabritziev, SA ;

Singh, BN ;

Tahtinen, S ;

Zinkle, SJ .

JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :668-672

[5]

Li M, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 4: RADIATION EFFECTS IN STRUCTURAL AND FUNCTIONAL MATERIALS FOR FISSION AND FUSION REACTORS, P667, DOI 10.1016/B978-0-08-056033-5.00122-1

[6]

Lyakishev N. P., 1996, HDB PHASE DIAGRAMS B, V1

[7]

Nikolaev A. K., 1983, CHROMIUM BRONZES

[8]

Nikolaev A. K., 2012, COPPER HEAT RESISTAN

[9] Heat treatment effects on the microstructure and properties of Cu-Cr-Zr alloy used for the ITER blanket components [J].

Suvorova, A. A. ;

Danilov, I. V. ;

Kalinin, G. M. ;

Korostelev, A. B. .

NUCLEAR MATERIALS AND ENERGY, 2018, 15 :80-84

← 1 →