Accelerated materials evaluation for nuclear applications

被引：20

作者：

Griffiths, M. ^{[1
]}

Walters, L. ^{[2
]}

Greenwood, L. R. ^{[3
]}

Garner, F. A. ^{[4
]}

机构：

[1] Queens Univ, Dept Mech & Mat Engn, Kingston, ON K7L 3N6, Canada

[2] Canadian Nucl Labs, Chalk River, ON K0J 1J0, Canada

[3] Pacific Northwest Natl Lab, Richland, WA 99352 USA

[4] Radiat Effects Consulting, Richland, WA 99352 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2017年 / 488卷

关键词：

AUSTENITIC STAINLESS-STEELS; FISSION-FUSION CORRELATIONS; NEUTRON-IRRADIATION; MICROSTRUCTURAL EVOLUTION; DISPLACEMENT CASCADES; STRUCTURAL-MATERIALS; BULK RECOMBINATION; VANADIUM ALLOYS; COPPER-ALLOYS; FAST-REACTOR;

D O I：

10.1016/j.jnucmat.2017.02.039

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

This paper addresses the opportunities and complexities of using materials test reactors with high neutron fluxes to perform accelerated studies of material aging in power reactors operating at lower neutron fluxes and with different neutron flux spectra. Radiation damage and gas production in different reactors have been compared using the code, SPECTER. This code provides a common standard from which to compare neutron damage data generated by different research groups using a variety of reactors. Crown Copyright (C) 2017 Published by Elsevier B.V. All rights reserved.

引用

页码：46 / 62

页数：17

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