Published April 2016 | Version v1
Book Metadata-only

Influence of pressurized water reactor environments on corrosion fatigue cracking behavior of Inconel 690(TT)

Creators

  • 1. Science and Technology on Reactor Full and Materials Laboratory, Nuclear Power Institute of China, Chengdu (China)

Description

Inconel 690(TT) is one of the key materials for tubes of steam generators for pressurized water reactor, where it is susceptible to corrosion fatigue cracking. In this paper, influence of pressurized water reactor environments on corrosion fatigue cracking behavior of Inconel 690(TT) was investigated under small scale yielding conditions. It was found that the accelerating effect of pressurized water reactor environments on corrosion fatigue crack growth rates was significant and this effect was more pronounced in the simulated primary water. In addition, out-of-plane cracking of corrosion fatigue cracks was correlated with pressurized water reactor environments and influenced the corrosion fatigue cracking behavior significantly. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Nuclear Material sub-volume

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-7103-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Nuclear Material sub-volume
Imprint Pagination
381 p.
Journal Page Range
p. 19-24

Conference

Title
2015 academic annual meeting of China Nuclear Society
Dates
21-24 Sep 2015
Place
Mianyang (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53085085
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION FATIGUE; CRACK PROPAGATION; CRACKING; CRACKS; ENVIRONMENT; INCONEL 690; PWR TYPE REACTORS; SIMULATION; STEAM GENERATORS; TUBES; WATER
Descriptors DEC
ALLOY-NI59CR30FE9; ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DECOMPOSITION; ENRICHED URANIUM REACTORS; FATIGUE; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; OXYGEN COMPOUNDS; POWER REACTORS; PYROLYSIS; REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 figs., 2 tabs., 9 refs.