You need JavaScript to view this

Creep crack growth in a reactor pressure vessel steel at 360 deg C

Abstract

Plain creep (PC) and creep crack growth (CCG) tests at 360 deg C and post metallography were carried out on a low alloy reactor pressure vessel steel (ASTM A508 class 2) with different microstructures. Lives for the CCG tests were shorter than those for the PC tests and this is more pronounced for simulated heat affected zone microstructure than for the parent metal at longer lives. For the CCG tests, after initiation, the cracks grew constantly and intergranularly before they accelerated to approach rupture. The creep crack growth rate is well described by C*. The relations between reference stress, failure time and steady crack growth rate are presented for the CCG tests. It is demonstrated that the failure stress due to CCG is considerably lower than the yield stress at 360 deg C. Consequently, the CCG will control the static strength of a reactor vessel. (orig.) 17 refs.
Authors:
Wu, Rui; Seitisleam, F; Sandstroem, R [1] 
  1. Swedish Institute for Metals Research, Stockholm (Sweden)
Publication Date:
Dec 31, 1998
Product Type:
Conference
Report Number:
VTT-SYMP-185(v.2); CONF-980999-
Reference Number:
SCA: 200104; 360103; PA: FI-99:003087; EDB-99:034963; SN: 99002064701
Resource Relation:
Conference: 4. Baltica seminar on plant maintenance for managing life and performance, Helsinki (Finland), 7-9 Sep 1998; Other Information: PBD: 1998; Related Information: Is Part Of BALTICA IV. Plant maintenance for managing life and performance; Hietanen, S.; Auerkari, P. [eds.] [VTT Manufacturing Technology, Espoo (Finland). Operational Reliability]; PB: 398 p.
Subject:
20 FOSSIL-FUELED POWER PLANTS; 36 MATERIALS SCIENCE; FOSSIL-FUEL POWER PLANTS; CREEP; CRACK PROPAGATION; PRESSURE VESSELS; STEEL-ASTM-A508; MICROSTRUCTURE; HEAT AFFECTED ZONE; TEMPERATURE RANGE 0400-1000 K; MATERIALS TESTING
OSTI ID:
325008
Research Organizations:
Technical Research Centre of Finland, Espoo (Finland)
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE99730863; ISBN 951-38-4577-X; TRN: FI9903087
Availability:
OSTI as DE99730863
Submitting Site:
FI
Size:
pp. 623-635
Announcement Date:

Citation Formats

Wu, Rui, Seitisleam, F, and Sandstroem, R. Creep crack growth in a reactor pressure vessel steel at 360 deg C. Finland: N. p., 1998. Web.
Wu, Rui, Seitisleam, F, & Sandstroem, R. Creep crack growth in a reactor pressure vessel steel at 360 deg C. Finland.
Wu, Rui, Seitisleam, F, and Sandstroem, R. 1998. "Creep crack growth in a reactor pressure vessel steel at 360 deg C." Finland.
@misc{etde_325008,
title = {Creep crack growth in a reactor pressure vessel steel at 360 deg C}
author = {Wu, Rui, Seitisleam, F, and Sandstroem, R}
abstractNote = {Plain creep (PC) and creep crack growth (CCG) tests at 360 deg C and post metallography were carried out on a low alloy reactor pressure vessel steel (ASTM A508 class 2) with different microstructures. Lives for the CCG tests were shorter than those for the PC tests and this is more pronounced for simulated heat affected zone microstructure than for the parent metal at longer lives. For the CCG tests, after initiation, the cracks grew constantly and intergranularly before they accelerated to approach rupture. The creep crack growth rate is well described by C*. The relations between reference stress, failure time and steady crack growth rate are presented for the CCG tests. It is demonstrated that the failure stress due to CCG is considerably lower than the yield stress at 360 deg C. Consequently, the CCG will control the static strength of a reactor vessel. (orig.) 17 refs.}
place = {Finland}
year = {1998}
month = {Dec}
}