Published April 2018 | Version v1
Book

Research on Co of primary circuit corrosion products in pressurized water reactor

  • 1. Nuclear and Radiation Safety Center, MEP, Beijing (China)
  • 2. China Nuclear Power Engineering Co., Ltd., Beijing (China)

Description

Corrosion products is an important part of source term in pressurized water reactor. The research of corrosion products source term influence factors and change rules play an important role on the controlling the source terms and shielding design. In this paper, taking a nuclear power plant as an example, we use CORA code to calculate the average activity of corrosion products in the primary circuit coolant and carry on the preliminary analysis to the influence factors of corrosion products. The calculation results show that the cobalt content in steam generator tubes, PH value of core coolant, the coolant purification efficiency and power can effectively control the yield of corrosion products. These research can provide guidance for reducing the irradiation of source term. (authors)

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.5--Radiation Protection 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.5--Radiation Protection sub-volume
Imprint Pagination
211 p.
Journal Page Range
p. 41-46

Conference

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

Optional Information

Notes
1 fig., 6 tabs., 7 refs.