Corrosion and microstructural analysis data for AISI 316L and AISI 347H stainless steels after exposure to a supercritical water environment

被引:4
作者
Ruiz, A. [1 ]
Timke, T. [1 ]
de Sande, A. van [1 ]
Heftrich, T. [1 ]
Novotny, R. [1 ]
Austin, T. [1 ]
机构
[1] European Commiss, Joint Res Ctr, Inst Energy & Transport, Westerduinweg 3, NL-1755 LE Petten, Netherlands
来源
DATA IN BRIEF | 2016年 / 7卷
关键词
Supercritical water reactor; SCWR; General corrosion; Austenitic stainless steel; Microstructural analysis;
D O I
10.1016/j.dib.2016.04.013
中图分类号
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号
07 ; 0710 ; 09 ;
摘要
This article presents corrosion data and microstructural analysis data of austenitic stainless steels AISI 316L and AISI 347H exposed to supercritical water (25 MPa, 550 degrees C) with 2000 ppb of dissolved oxygen. The corrosion tests lasted a total of 1200 h but were interrupted at 600 h to allow measurements to be made. The microstructural data have been collected in the grain interior and at grain boundaries of the bulk of the materials and at the superficial oxide layer developed during the corrosion exposure. (C) 2016 The Authors. Published by Elsevier Inc.
引用
收藏
页码:1341 / 1348
页数:8
相关论文
共 3 条
[1]  
Novotny R., 2016, J NUCL ENG RAD SCI
[2]   European supercritical water cooled reactor [J].
Schulenberg, T. ;
Starflinger, J. ;
Marsault, P. ;
Bittermann, D. ;
Maraczy, C. ;
Lauriene, E. ;
Nijeholt, J. A. Lycklama a ;
Anglart, H. ;
Andreani, M. ;
Ruzickova, M. ;
Toivonen, A. .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) :3505-3513
[3]   Corrosion and stress corrosion cracking in supercritical water [J].
Was, G. S. ;
Ampornrat, P. ;
Gupta, G. ;
Teysseyre, S. ;
West, E. A. ;
Allen, T. R. ;
Sridharan, K. ;
Tan, L. ;
Chen, Y. ;
Ren, X. ;
Pister, C. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) :176-201