TY - JOUR
T1 - Stress Corrosion Cracking of Nuclear Pressure Vessel Steels in Pressurized High Temperature Waters
AU - Shoji, Tetsuo
AU - Aizawa, Syuji
AU - Takahashi, Hideaki
N1 - Copyright:
Copyright 2016 Elsevier B.V., All rights reserved.
PY - 1988
Y1 - 1988
N2 - The quantitative evaluation of the subcritical erack growth behavior of nuclear pressure vessels and piping steels in pressurized high temperature water has been receiving extensive attention to ensure the structual integrity of nuclear pressure vessels and piping. Recent research progress in this field suggests the significance of the sulfur content of steels in assessing susceptibility to environmentally assisted cracking of these steels in high temperature water from the view point of solution chemistry at a crack tip, where dissolution of MnS, non-metallic inclusion, results in an enrichment of S anion, such as SO42-. Hence, it is neccesary to simulate the solution chemisty at a crack tip for the slow strain rate test (SSRT) by use of a smooth specimen which has been commonly used as a useful tool to see stress corrosion cracking characteristics in a short time. In this study, SSRT tests are performed in simulated BWR or PWR environments, and specimen electrochemical potentials are controlled chemically or potentiostatically. The cracking potential of this material/environments systems are examined quantitatively as a function of temperature, sulfur content in steels and also SO42- contents in solution, simulating crack tip solution chemistry. Cracking potential showed a lower value of about 250°C, rather than 288°C. Sulfur content of steel and SO42- concentration in solution can drastically influence the cracking potential and some amount of sulfur in steels or SO42- anion at a crack tip make it possible to crack at a BWR or PWR condition.
AB - The quantitative evaluation of the subcritical erack growth behavior of nuclear pressure vessels and piping steels in pressurized high temperature water has been receiving extensive attention to ensure the structual integrity of nuclear pressure vessels and piping. Recent research progress in this field suggests the significance of the sulfur content of steels in assessing susceptibility to environmentally assisted cracking of these steels in high temperature water from the view point of solution chemistry at a crack tip, where dissolution of MnS, non-metallic inclusion, results in an enrichment of S anion, such as SO42-. Hence, it is neccesary to simulate the solution chemisty at a crack tip for the slow strain rate test (SSRT) by use of a smooth specimen which has been commonly used as a useful tool to see stress corrosion cracking characteristics in a short time. In this study, SSRT tests are performed in simulated BWR or PWR environments, and specimen electrochemical potentials are controlled chemically or potentiostatically. The cracking potential of this material/environments systems are examined quantitatively as a function of temperature, sulfur content in steels and also SO42- contents in solution, simulating crack tip solution chemistry. Cracking potential showed a lower value of about 250°C, rather than 288°C. Sulfur content of steel and SO42- concentration in solution can drastically influence the cracking potential and some amount of sulfur in steels or SO42- anion at a crack tip make it possible to crack at a BWR or PWR condition.
KW - Cracking Potential
KW - Fracture
KW - Nuclear Pressure Vessel Steels
KW - Slow Strain Rate Test
KW - Stress Corrosion Cracking
KW - Subcritical Crack Growth
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U2 - 10.1299/kikaia.54.1251
DO - 10.1299/kikaia.54.1251
M3 - Article
AN - SCOPUS:0024019145
VL - 54
SP - 1251
EP - 1257
JO - Nihon Kikai Gakkai Ronbunshu, A Hen/Transactions of the Japan Society of Mechanical Engineers, Part A
JF - Nihon Kikai Gakkai Ronbunshu, A Hen/Transactions of the Japan Society of Mechanical Engineers, Part A
SN - 0387-5008
IS - 502
ER -