Risk Evaluation of Flow-Accelerated Corrosion Based on One-Dimensional FAC Code-Reference-Cited by-同舟云学术

Risk Evaluation of Flow-Accelerated Corrosion Based on One-Dimensional FAC Code

Published:2013-08 Issue:2 Volume:183 Page:194-209
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Suzuki Hiroaki¹,Uchida Shunsuke¹,Naitoh Masanori¹,Okada Hidetoshi¹,Koikari Soji¹,Hasegawa Kunio²,Kojima Fumio³,Koshizuka Seiichi⁴,Lister Derek H.⁵

Affiliation:

1. Institute of Applied Energy, 1-14-2, Nishi-Shimbashi, Minato-ku, Tokyo, 105-0001, Japan

2. Japan Nuclear Energy Safety Organization, 1-28, Toranomon 4-chome, Minato-ku Tokyo 105-0001, Japan

3. Kobe University, 1-1, Rokkodai-machi, Nada-ku, Kobe, 657-8501, Japan

4. University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo, 113-8656, Japan

5. University of New Brunswick, P.O. Box 4400, Fredericton New Brunswick E3B 5A3, Canada

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT13-A18111

Reference23 articles.

1. “Secondary Piping Rupture Accident at Mihama Power Station, Unit 3, of the Kansai Electric Power Co., Inc. (Final Report), Rev. 1,” Nuclear and Industrial Safety Agency (2005) (translated by the Japan Nuclear Energy Safety Organization ).

2. L. E. SANCHEZ-CALDERA, “The Mechanism of Corrosion-Erosion in Steam Extraction Lines of Power Stations,” PhD Thesis, Department of Mechanical Engineering, Massachusetts Institute of Technology (1984).

3. Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I)

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Probabilistic evaluation of EMAR signals to evaluate pipe wall thickness and its application to pipe wall thinning management;NDT & E International;2021-09

2. Improvement of plant reliability based on combining of prediction and inspection of crack growth due to intergranular stress corrosion cracking;Nuclear Engineering and Design;2019-01

3. Improvement of plant reliability based on combination of prediction and inspection of wall thinning due to FAC;Nuclear Engineering and Design;2018-10

4. Verification and validation procedures of calculation codes for determining corrosive conditions in the BWR primary cooling system based on water radiolysis and mixed potential models;Journal of Nuclear Science and Technology;2013-10-07