Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects

被引：79

作者：

Barabash, V. R. ^{[1
]}

Kalinin, G. M. ^{[2
]}

Fabritsiev, S. A. ^{[3
]}

Zinkle, S. J. ^{[4
]}

机构：

[1] ITER Org, F-13115 St Paul Les Durance, France

[2] RDIPE, Moscow 101000, Russia

[3] DV Efremov Sci Res Inst Electrophys Apparatus, St Petersburg 196641, Russia

[4] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2011年 / 417卷 / 1-3期

关键词：

COPPER-ALLOYS; COMPONENTS; ITER;

D O I：

10.1016/j.jnucmat.2010.12.158

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Precipitation hardened CuCrZr alloy is a promising heat sink and functional material for various applications in ITER, for example the first wall, blanket electrical attachment, divertor, and heating systems. Three types of thermo-mechanical treatment were identified as most promising for the various applications in ITER: solution annealing, cold working and ageing; solution annealing and ageing; solution annealing and ageing at non-optimal condition due to specific manufacturing processes for engineering-scale components. The available data for these three types of treatments were assessed and minimum tensile properties were determined based on recommendation of Structural Design Criteria for the ITER In-vessel Components. The available data for these heat treatments were analyzed for assessment of neutron irradiation effect. Using the definitions of the ITER Structural Design Criteria the design allowable stress intensity values are proposed for CuCrZr alloy after various heat treatments. (C) 2010 EURATOM. Published by Elsevier B.V. All rights reserved.

引用

页码：904 / 907

页数：4

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