Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Jun Min Seo"'
Publikováno v:
Crystals, Vol 14, Iss 2, p 197 (2024)
Three new mixed metal fluoride hydrates, M2+AlF5(H2O)7 (M2+ = Fe2+, Co2+, or Ni2+), were synthesized and characterized. The crystals of M2+AlF5(H2O)7 were obtained using a hydrothermal method with a CF3COOH aqueous solution. The crystal structures di
Externí odkaz:
https://doaj.org/article/a6e39f0cc7f34ed68861cffc398a1761
Autor:
Jun-Min Seo, Hune-Tae Kim, Yun-Jae Kim, Hiroyuki Yamada, Tomohisa Kumagai, Hayato Tokunaga, Naoki Miura
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 7, Pp 2386-2394 (2022)
In this paper, smooth and notched bar tensile tests of austenitic stainless steel 304 are performed, covering four different multi-axial stress states and six different strain rate conditions, to investigate the effect of the stress triaxiality and s
Externí odkaz:
https://doaj.org/article/15f6e38ca1644699b821993f22b5cff0
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1726-1746 (2022)
This paper presents fracture mechanics analysis results for various cracks located at pressurized water reactor pressure vessel nozzle crotch corners taking into consideration constraint effect. Technical documents such as the ASME B&PV Code, Sec.XI
Externí odkaz:
https://doaj.org/article/de9c7186f5964770bfd8d7deb38f0d8e
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 3, Pp 1098-1108 (2022)
The effect of the material hardening model of the canister on a finite element vertical cask drop simulation is investigated for the strain-based acceptance evaluation. Three different hardening models are considered in this paper: the isotropic hard
Externí odkaz:
https://doaj.org/article/743ddae0328f48288a8dcb917ef9d62d
Publikováno v:
Nuclear Engineering and Technology. 54:1726-1746
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b74e9d79ebb02951d6fa718bb45f006
https://doi.org/10.1016/j.net.2021.11.022
https://doi.org/10.1016/j.net.2021.11.022
Publikováno v:
Nuclear Engineering and Technology. 54:1098-1108
The effect of the material hardening model of the canister on a finite element vertical cask drop simulation is investigated for the strain-based acceptance evaluation. Three different hardening models are considered in this paper: the isotropic hard
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::feb09ad612ec45cbcef214e9a8dd60fa
https://doi.org/10.1016/j.net.2021.09.006
https://doi.org/10.1016/j.net.2021.09.006
Autor:
Jun-Min Seo, Hune-Tae Kim, Yun-Jae Kim, Hiroyuki Yamada, Tomohisa Kumagai, Hayato Tokunaga, Naoki Miura
Publikováno v:
Volume 4B: Materials and Fabrication.
In this study, Johnson-Cook fracture strain model considering the effect of stress triaxiality and strain rate is determined for austenitic stainless steel 304. Tensile test data of four different stress triaxiality and six different strain rate cond
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dc06216224be9fb3653675536591f02d
https://doi.org/10.1115/pvp2022-83772
https://doi.org/10.1115/pvp2022-83772
Publikováno v:
Volume 4B: Materials and Fabrication.
In this paper, a strain-based failure assessment is performed on a canister made of stainless steel when a spent nuclear fuel dry storage system goes through a drop accident, to investigate the effects of strain rate on strain-based failure assessmen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7d286c47b5fcf56554b3f79022f212f9
https://doi.org/10.1115/pvp2022-83765
https://doi.org/10.1115/pvp2022-83765
Publikováno v:
Engineering Fracture Mechanics. 260:108188
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::62c550961083a77b45852c7c598310f1
https://doi.org/10.1016/j.engfracmech.2021.108188
https://doi.org/10.1016/j.engfracmech.2021.108188
Publikováno v:
Volume 1: Codes and Standards.
In this paper, allowable bending moments for circumferential inner surface cracked pipes are evaluated. ASME Boiler and Pressure Vessel code Section XI, “Rules for Inspection of Nuclear Power Plant Components” provides analytical evaluation proce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ddd431e093fae4521bc9675fb198941
https://doi.org/10.1115/pvp2019-93553
https://doi.org/10.1115/pvp2019-93553