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pro vyhledávání: '"Bengt O. Y. Lydell"'
Autor:
Tatjana Jevremovic, Bengt O. Y. Lydell, Robertas Alzbutas, Xinjian Duan, Jürgen Sievers, Klaus Heckmann, Min Wang
Probabilistic fracture mechanics (PFM) simulates the behavior of cracked structures and propagates uncertainties from input parameters to a failure probability or its uncertain estimate. In nuclear technology, this approach supports the assessment of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::99e7384fba39ef2985aafc83026d7426
https://vb.ktu.edu/KTU:ELABAPDB89982271&prefLang=en_US
https://vb.ktu.edu/KTU:ELABAPDB89982271&prefLang=en_US
Autor:
Cole Takasugi, Klaus Heckmann, Jürgen Sievers, Tatjana Jevremovic, Seyed Reihani, Sai Zhang, Pegah Farshadmanesh, Zahra Mohaghegh, Julia Abdul Karim, Bengt O. Y. Lydell, Xinjian Duan, Ernie Kee, Wen Chi Cheng, Chokri Zammali, Tatsuya Sakurahara, Robertas Alzbutas, Gyeong Geun Lee, Xian Xun Yuan, Vladimir Morozov
Publikováno v:
Progress in Nuclear Energy. 118:103105
This paper presents the first output of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP), titled Methodology for Assessing Pipe Failure Rates in Advanced Water-Cooled Reactors (AWCRs), launched in 2018. This IAEA CRP i
Autor:
Karl N. Fleming, Bengt O. Y. Lydell
Publikováno v:
Reliability Engineering & System Safety. 86:227-246
Estimates of failure rates for nuclear power plant piping systems are important inputs to Probabilistic Risk Assessments (PRA) and risk informed applications of PRA. Such estimates are needed for initiating event frequencies for Loss of Coolant Accid
Autor:
Bengt O. Y. Lydell
Publikováno v:
Reliability Engineering & System Safety. 68:207-217
Almost twenty years ago, in Volume 2 of Reliability Engineering (the predecessor of Reliability Engineering and System Safety ), a paper by H. M. Thomas of Rolls Royce & Associates Ltd. presented a generalized approach to the estimation of piping and
Autor:
Bengt O. Y. Lydell
Publikováno v:
Reliability Engineering & System Safety. 55:257-260
Publikováno v:
Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co.
Autor:
Bengt O. Y. Lydell, Karl N. Fleming
Publikováno v:
12th International Conference on Nuclear Engineering, Volume 1.
Markov model theory has been applied to develop a method to evaluate the influence of alternate strategies for in-service inspection and leak detection on the frequency of leaks and ruptures in nuclear power plant piping systems [1–4]. This approac