Modeling Irradiation Damage in Zr-2.5Nb and Its Effects on Delayed Hydride Cracking Growth Rate

被引：6

作者：

Bickel, G. A. ^{[1
]}

Griffiths, M. ^{[1
]}

Chaput, H. ^{[1
]}

Buyers, A. ^{[1
]}

Coleman, C. E. ^{[1
]}

机构：

[1] AECL Chalk River Labs, Chalk River, ON K0J 1J0, Canada

来源：

ZIRCONIUM IN THE NUCLEAR INDUSTRY | 2015年 / 1543卷

关键词：

Zr-2.5Nb; neutron irradiation; delayed hydride cracking; pressure tubes; microstructure; X-ray diffraction; line broadening; beta-phase; PRESSURE TUBES; ZIRCONIUM ALLOYS; BEHAVIOR; MICROSTRUCTURE;

D O I：

10.1520/STP154320120157

中图分类号：

TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

Zr-2.5Nb is a dual-phase alloy consisting of an hcp (alpha) phase containing up to 1 wt. % Nb and a bcc (beta) phase containing about 20 wt. % Nb. The alpha phase constitutes the majority of the material volume. For in-service Zr-2.5Nb CANDU pressure tubes, the structures of both the alpha and beta phases evolve as a result of the effects of irradiation and operating temperature: dislocation loop formation in the alpha phase and decomposition or reconstitution of the beta phase. X-ray diffraction data are used to study the irradiation damage (represented by the integral breadth of hcp diffraction peaks and the lattice parameter of the beta phase). This evolution of the microstructure must be modeled as a function of operating conditions so that the state of the microstructure of in-service pressure tubes can be predicted. Delayed hydride cracking (DHC) growth rates in Zr-2.5Nb CANDU pressure tube material also depends on the state of the microstructure. In this paper, it is shown that the majority of the DHC growth rate changes can be ascribed to thermal and irradiation effects on the microstructure.

引用

页码：800 / 829

页数：30

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