skip to main content

Title: A predictive model for corrosion fatigue crack growth rates in RPV steels exposed to PWR environments

Corrosion fatigue crack propagation rates have been measured in A533B Class 1 plate in stagnant PWR primary water for a range of steel sulphur contents, temperature and corrosion potential values. Parametric descriptions of the data collected under constant rig conditions give good correlations for each variable and are consistent with a crack tip environment controlled process related to sulphur chemistry. A modified crack velocity equation is proposed to include temperature, sulphur content, polarization potential, frequency and {Delta}K values and it is shown how the predictions compare with the proposed ASME XI revision. Critical fatigue situations are identified for 0.003% and 0.019% sulphur steels typical of modern and old plant. The use of the equation in assessing the synergistic effect of variables is discussed.
Authors:
; ;  [1]
  1. Sheffield Hallam Univ. (United Kingdom). School of Engineering
Publication Date:
OSTI Identifier:
191339
Report Number(s):
CONF-950740--
ISBN 0-7918-1337-1; TRN: IM9610%%340
Resource Type:
Book
Resource Relation:
Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of Fatigue and crack growth: Environmental effects, modeling studies, and design considerations. PVP-Volume 306; Yukawa, S. [ed.] [Yukawa (Sumio), Boulder, CO (United States)]; Jones, D.P. [ed.] [Bettis Atomic Power Lab., West Mifflin, PA (United States)]; Mehta, H.S. [ed.] [GE Nuclear Energy, San Jose, CA (United States)]; PB: 331 p.
Publisher:
American Society of Mechanical Engineers, New York, NY (United States)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; PRESSURE VESSELS; REACTOR MATERIALS; STEEL-ASTM-A533-B; CORROSION FATIGUE; CRACK PROPAGATION; PRIMARY COOLANT CIRCUITS; PARAMETRIC ANALYSIS; MATHEMATICAL MODELS; EXPERIMENTAL DATA; TEMPERATURE DEPENDENCE; SULFUR ADDITIONS; STRESS INTENSITY FACTORS; STRESS CORROSION