A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency-Reference-Cited by-同舟云学术

A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency

Published:2012-02 Issue:2 Volume:170 Page:136-150
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Chatterjee Kaushik¹,Modarres Mohammad¹

Affiliation:

1. University of Maryland College Park, Department of Mechanical Engineering Center for Risk and Reliability, College Park, Maryland 20742

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE11-27

Reference25 articles.

1. Flow-induced vibration and fretting-wear predictions of steam generator helical tubes

2. NUREG-0933, “Resolution of Generic Safety Issues: Issue 188: Steam Generator Tube Leaks or Ruptures, Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches” U.S. Nuclear Regulatory Commission (Aug. 2010).

3. “Rapidly Propagating Fatigue Cracks in Steam Generator Tubes,” Bulletin 88-02, U.S. Nuclear Regulatory Commission (Feb. 5, 1988).

Cited by 15 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. A multi-state Semi-Markov model for nuclear power plants piping systems subject to fatigue damage and random shocks under dynamic environments;International Journal of Fatigue;2023-03

2. A review of probabilistic structural integrity assessment in the nuclear sector and possible future directions;Fatigue & Fracture of Engineering Materials & Structures;2021-09-23

3. Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator;Nuclear Engineering and Technology;2021-09

4. Joint optimization of safety barriers for enhancing business continuity of nuclear power plants against steam generator tube ruptures accidents;Reliability Engineering & System Safety;2020-10

5. Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants;Progress in Nuclear Energy;2020-01