Response of nanoclusters in a 9Cr ODS steel to 1 dpa, 525 °C proton irradiation

被引：66

作者：

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

Field, K. G. ^{[1
]}

Allen, T. R. ^{[1
]}

Miller, M. K. ^{[2
]}

Bentley, J. ^{[2
]}

Busby, J. T. ^{[2
]}

机构：

[1] Univ Wisconsin, Mat Sci Program, Madison, WI 53706 USA

[2] Oak Ridge Natl Lab, Div Mat Sci & Technol, Oak Ridge, TN 37831 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2010年 / 407卷 / 01期

关键词：

FERRITIC ALLOYS; NEUTRON-IRRADIATION; STABILITY;

D O I：

10.1016/j.jnucmat.2010.07.002

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Ferritic-martensitic (F/M) alloys are expected to play an important role as cladding or structural components in Generation IV and other advanced nuclear systems operating in the temperature range 350-700 degrees C and to doses up to 200 displacements per atom (dpa) Oxide dispersion strengthened (ODS) F/M steels have been developed to operate at higher temperatures than traditional F/M steels These steels contain nanometer-sized Y-Ti-O nanoclusters for additional strengthening A proton irradiation to 1 dpa at 525 degrees C has been performed on a 9Cr ODS steel to determine the nanocluster stability at low dose The evolution of the nanocluster population and the composition at the nanocluster-matrix Interface were studied using electron microscopy and atom probe tomography The data from this study are contrasted to those from a previous study on heavy-ion irradiated 9Cr ODS steel (C) 2010 Elsevier B V All rights reserved

引用

页码：2 / 9

页数：8

共 23 条

[1] Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation [J].

Allen, T. R. ;

Gan, J. ;

Cole, J. I. ;

Miller, M. K. ;

Busby, J. T. ;

Shutthanandan, S. ;

Thevuthasan, S. .

JOURNAL OF NUCLEAR MATERIALS, 2008, 375 (01) :26-37

[2]

Bentley J., 2000, Microscopy and Microanalysis, V6, P1186

[3]

BENTLEY J, 2007, MICROSC MICROANAL S2, V13, P1072

[4]

Bentley J., 2008, MICROSC MICROANAL, V14, P1416

[5]

Bentley J., 2004, MICROSC MICROANAL, V10, P662

[6] Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure [J].

Garner, FA ;

Toloczko, MB ;

Sencer, BH .

JOURNAL OF NUCLEAR MATERIALS, 2000, 276 (01) :123-142

[7]

Hellman OC, 2000, MICROSC MICROANAL, V6, P437, DOI 10.1007/s100050010051

[8] GROUPS OF GALAXIES .1. NEARBY GROUPS [J].

HUCHRA, JP ;

GELLER, MJ .

ASTROPHYSICAL JOURNAL, 1982, 257 (02) :423-437

[9]

HYDE JM, 2001, MAT RES SOC P, V650, P6

[10] Characterization of precipitates in MA/ODS ferritic alloys [J].

Miller, M. K. ;

Russell, K. F. ;

Hoelzer, D. T. .

JOURNAL OF NUCLEAR MATERIALS, 2006, 351 (1-3) :261-268

← 1 2 3 →