Zobrazeno 1 - 10
of 51
pro vyhledávání: '"Xinjian Duan"'
Autor:
Klaus Heckmann, Dong-Hyun Ahn, John Beal, Wen-Chi Cheng, Xinjian Duan, Tatjana Jevremovic, Ernie Kee, Zahra Mohaghegh, Bengt Lydell, Seyed Reihani, Tatsuya Sakurahara, Min Wang
Publikováno v:
Nuclear Engineering and Design. 398:111990
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:
Xinjian Duan, Yifan Huang
Publikováno v:
Volume 1: Codes and Standards.
The deterministic leak-before-break (LBB) analysis and probabilistic fracture mechanics (PFM) assessment are two primary approaches for demonstrating extremely low probability of rupture of pressurized piping in the nuclear energy industry. Both stre
Autor:
Xinjian Duan, Dongmei Sun
Publikováno v:
Volume 6B: Materials and Fabrication.
The dissimilar metal weld (DMW) is widely used in fabrication and manufacturing in various industries. Joining between nickel-based alloy and ferritic steel tubing and piping is commonly employed for ASME Code compliant welds for high-temperature and
Publikováno v:
Theoretical and Applied Fracture Mechanics. 108:102595
This paper presents a direct weight function-based method to evaluate the crack opening displacement (COD) which is a key parameter in leak-before-break (LBB) assessment and in probabilistic fracture mechanics (PFM) assessment of nuclear piping syste
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
Publikováno v:
Volume 1B: Codes and Standards.
A recent surge of nuclear industry interest in the development of smaller, modular/factory-built nuclear reactors has been underway for the last few years. Recently, the Canadian Nuclear Safety Commission (CNSC), which is the Canadian nuclear regulat
Publikováno v:
Volume 6B: Materials and Fabrication.
The dissimilar metal welds between the Inconel 600 flow element and the SA-106 Grade B carbon pipe with Alloy 82 or Alloy 182 filler material of some CANDU® designs have been identified as being susceptible to Primary Water Stress Corrosion Cracking
Publikováno v:
Nuclear Engineering and Design. 281:154-162
A probabilistic structural integrity assessment framework utilizing a two-loop Monte Carlo simulation process is proposed. The process and interpretation of the results are demonstrated using an example of Steam Generator (SG) tubing with fretting fl
Publikováno v:
Volume 1A: Codes and Standards.
A new degradation mechanism has been observed in Monel 400 Steam Generator tubing material, a nickel-copper alloy (63Ni-28Cu-2½Fe) with the ASME material designation SB-163/N04400. The location is above the top preheater support plate of the two re-