Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Min-Gu Won"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 1-8 (2024)
In this study, the influence of thermal aging on structural integrity is investigated for Gr. 91 steel. A commercial grade Gr. 91 steel is used for the virgin material, and service-exposed Gr. 91 steel is sampled from a steam pipe of a super critical
Externí odkaz:
https://doaj.org/article/b35e920a39514aa6823892f612f95043
Autor:
Jin Haeng Lee, Yeong-Garp Cho, Hyokwang Lee, Chang-Gyu Park, Jong-Myeong Oh, Yeon-Sik Yoo, Min-Gu Won, Hyung Huh
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4477-4490 (2023)
Fuel locking mechanisms (FLMs) are essential in upward-flow research reactors to prevent accidental fuel separation from the core during reactor operation. This study presents a novel design concept for a remotely controlled plate-type nuclear fuel l
Externí odkaz:
https://doaj.org/article/d95039b646c04d4280481d91ecab9313
Publikováno v:
Fatigue & Fracture of Engineering Materials & Structures. 42:494-503
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::960396e8fc4ea10b8e850e3e4245ac37
https://doi.org/10.1111/ffe.12925
https://doi.org/10.1111/ffe.12925
Publikováno v:
Journal of Mechanical Science and Technology. 32:1143-1151
We focused on the modeling of the high-temperature Stress relaxation (SR) curves for Gr. 91 steel using two nonlinear models of a spring-dashpot and Peleg model to get a better fit to experimental relaxation data. A series of SR tests were performed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f73246d8b71c75c1b690492026f0c36
https://doi.org/10.1007/s12206-018-0217-6
https://doi.org/10.1007/s12206-018-0217-6
Publikováno v:
Nuclear Engineering and Design. 324:181-195
A web-based design evaluation program is developed for the elevated temperature design (ETD) analysis according to the RCC-MRx for Generation IV and fusion reactor systems. The program, named ‘HITEP_RCC-MRx,’ is composed of two modules: ‘HITEP_
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5a952566f510bbe864e6ab62f3a60f6d
https://doi.org/10.1016/j.nucengdes.2017.08.034
https://doi.org/10.1016/j.nucengdes.2017.08.034
Publikováno v:
Journal of Pressure Vessel Technology. 141
An integrated software platform of high-temperature design evaluation and defect assessment for a nuclear component and piping system subjected to high-temperature operation in creep regime has been developed. The program, called “HITEP_RCC-MRx,”
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48ddde3d519c10948c53116aa18611dc
https://doi.org/10.1115/1.4043916
https://doi.org/10.1115/1.4043916
Publikováno v:
Nuclear Science and Techniques. 30
This study investigates the risks of non-conservative piping design according to ASME B31.1 for high-temperature piping subjected to long-term operation at high temperature in a creep regime based on a sensitivity analysis of the hold time. Design ev
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::123e142e5a71c975ab589fd63c57c726
https://doi.org/10.1007/s41365-019-0604-4
https://doi.org/10.1007/s41365-019-0604-4
Publikováno v:
International Journal of Pressure Vessels and Piping. 189:104292
The present paper provides engineering estimates for plastic J-integral and crack opening displacement (COD) of a non-idealized axial through-wall crack (TWC) in pipes based on detailed 3-dimensional finite element (FE) analyses. The behaviors of pla
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6ca30a1cd2ddf637b9c59e6eeacce869
https://doi.org/10.1016/j.ijpvp.2020.104292
https://doi.org/10.1016/j.ijpvp.2020.104292
Publikováno v:
International Journal of Pressure Vessels and Piping. 182:104074
In this study, creep elastic follow-up (EFU) factor solutions are developed for the piping design of high-temperature reactors. A straight pipe under combined primary and secondary loadings is considered for high-temperature piping. Axial tension, in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::119a015afafb1b06eaf84a915907380b
https://doi.org/10.1016/j.ijpvp.2020.104074
https://doi.org/10.1016/j.ijpvp.2020.104074
Publikováno v:
Volume 3A: Design and Analysis.
In this paper, the thermal stress characteristics of the pipe-in-pipe (PIP) system under high temperature condition are analyzed. The PIP is a type of pipe applied in sodium-cooled faster reactor (SFR) and has a different geometry from a single pipe.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ae69376b14de4f3d3bb52724745cf8c
https://doi.org/10.1115/pvp2018-84578
https://doi.org/10.1115/pvp2018-84578