Zobrazeno 1 - 10
of 45
pro vyhledávání: '"Chang-Kyun Oh"'
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers - A. 43:153-159
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e25b35f277800e1f305be2b90f903cad
https://doi.org/10.3795/ksme-a.2019.43.3.153
https://doi.org/10.3795/ksme-a.2019.43.3.153
Publikováno v:
Journal of Mechanical Science and Technology. 31:2243-2249
Owing to the fact that thermal fatigue is a well-known damage mechanism in nuclear power plants, accurate stress and fatigue evaluation are highly important. Operating experience shows that the design condition is conservative compared to the actual
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e1219ef44cf00372b2981ab0ab7ee6cb
https://doi.org/10.1007/s12206-017-0421-9
https://doi.org/10.1007/s12206-017-0421-9
Publikováno v:
Nuclear Engineering and Design. 313:10-19
Steam generator is one of the major components in a nuclear power plant, and it consists of thousands of thin-walled tubes. The operating record of the steam generators has indicated that a number of axial cracks due to stress corrosion have been fre
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1b3b147c8abdcc62caf625185af4bca8
https://doi.org/10.1016/j.nucengdes.2016.11.027
https://doi.org/10.1016/j.nucengdes.2016.11.027
Publikováno v:
Fusion Engineering and Design. :2172-2177
The ITER project is aimed at demonstrating the feasibility of fusion as one of the possible energy options. A layout optimization is one of the design concerns for maintaining safety and reliability of the piping, because some piping penetrating the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4e133bd371155aa6766fcf9340efa63
https://doi.org/10.1016/j.fusengdes.2014.11.020
https://doi.org/10.1016/j.fusengdes.2014.11.020
New Approach for Fatigue Damage Monitoring Based on Actual Operating History of Nuclear Power Plants
Publikováno v:
Nuclear Technology. 190:88-96
Metal fatigue is a well-known phenomenon whereby material characteristics are deteriorated when even a small load is applied repeatedly. Therefore, an accurate fatigue evaluation is very important ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::718415b1b0b840caf2611e05ff683003
https://doi.org/10.13182/nt13-150
https://doi.org/10.13182/nt13-150
Publikováno v:
Journal of the Korean Association of Geographic Information Studies. 18:64-73
Recently, the integrated utilization of technology with IT is in demand for the effectiveness of field management together with the prevention and prompt action on safety accident at construction site. In addition, the establishment of construction s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::481ee4d55d233bb649e59e7a42044c44
https://doi.org/10.11108/kagis.2015.18.1.064
https://doi.org/10.11108/kagis.2015.18.1.064
Publikováno v:
International Journal of Fracture. Jan2007, Vol. 143 Issue 2, p119-133. 15p. 3 Charts, 18 Graphs.
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 37:875-881
The failure of a bolted joint owing to stress corrosion cracking (SCC) has been considered one of the most important structural integrity issues in a nuclear power plant. In this study, the failure possibility of bolting, which is used to support the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::02d8dd708d406f6588bb709ea23a03ae
https://doi.org/10.3795/ksme-a.2013.37.7.875
https://doi.org/10.3795/ksme-a.2013.37.7.875
Publikováno v:
Volume 1A: Codes and Standards.
In accordance with the recommendation of USNRC and the U.S. license renewal experiences, the effect of reactor coolant environment on the fatigue life has to be considered for the continued operation of operating nuclear power plants as well as for t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::907e810f0fc156bf66b2b2794b1fe64a
https://doi.org/10.1115/pvp2016-63374
https://doi.org/10.1115/pvp2016-63374
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 34:97-101
2000년10월V.C. Summer 원전의가동중검사시원자로압력용기출구노즐에서원주방향균열이발견된이후,2003년9월Tsuruga 2호기의가압기방출노즐이종금속용접부에서PWSCC에의한누설이발견되었고, 2005
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71336f68d198343fc1952580d874aeb1
https://doi.org/10.3795/ksme-a.2010.34.1.97
https://doi.org/10.3795/ksme-a.2010.34.1.97