Published April 2018 | Version v1
Book

The research report of the risk assessment and treatment of PbSCC in 800 alloy heat transfer tube of NPP's steam generators

Creators

  • 1. CNNP, Nuclear Power Operations Management Co, Ltd, Haiyan, Zhejiang (China)

Description

Through the study of the latest foreign experience and results, the author preliminarily determines that the probability of lead induced stress corrosion cracking (PbSCC) of 800 alloy heat transfer tubes of TQNPP's steam generators is larger. The results of simulated immersion test of 800 alloy shows that the susceptibility of PbSCC in 800 alloy heat transfer tubes is very larger. The investigation of lead sources reveals that the main source of lead is the dissolution of lead in the material of secondary circuit and the use of leaded tools or articles, the investigation also finds that there is obvious lead deposition in the steam generator secondary side. In order to solve the problem, a series of countermeasures are studied and developed to reduce the stress corrosion susceptibility of 800 alloy lead and the rupture risk of heat transfer tubes. (author)

Part of:
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.3--Nuclear Energy & Power sub-volume

Additional details

Publishing Information

Publisher
China Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-8776-4
Imprint Title
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.3--Nuclear Energy & Power sub-volume
Imprint Pagination
602 p.
Journal Page Range
p. 100-112

Conference

Title
2017 academic annual meeting of China Nuclear Society
Dates
16-18 Oct 2017
Place
Weihai (China)

Optional Information

Notes
7 figs., 5 tabs., 13 refs.