Zobrazeno 1 - 10
of 627
pro vyhledávání: '"Yun-Jae Kim"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 7, Pp 2859-2874 (2024)
This paper presents the finite element deformation and failure simulation of a typical Korean high-power reactor vessel under a severe accident characterized by large break loss of coolant (LBLOCA) with in-vessel retention of molten corium through ex
Externí odkaz:
https://doaj.org/article/8e7545a1c2a1418491e4c83bca3bdc17
Autor:
Chaewon Jeong, Ji Ho Shin, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui Jang, Yun-Jae Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2131-2140 (2024)
The chloride-induced stress corrosion cracking (CISCC) is one of the major integrity concerns in dry storage canisters made of austenitic stainless steels (ASSs). In this study, an advanced duplex stainless steel (DSS) with a composition of Fe–19Cr
Externí odkaz:
https://doaj.org/article/4cc17309f06847ddb9a5592d065f9718
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1320-1329 (2024)
When wall-thinning occurs in nuclear Class 2 and 3 pipes, reinforcement is typically applied rather than replacement. To analyze the structural integrity of reinforced wall-thinned pipe, stress analysis results using full 3-D FE analysis are not comp
Externí odkaz:
https://doaj.org/article/07fd08fdc533492c8119cb0989754cda
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4647-4658 (2023)
In this paper, elastic-plastic fracture mechanics analysis is performed to determine the critical crack sizes of the multipurpose canister (MPC) manufactured using austenitic stainless steel under dynamic loading conditions that simulate drop acciden
Externí odkaz:
https://doaj.org/article/f4910b7175aa443896aa890ae4c1e9e6
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4146-4158 (2023)
This paper proposes a combined plastic and creep constitutive model of A533B1 pressure vessel steel to simulate progressive deformation of nuclear pressure vessels under severe accident conditions. To develop the model, recent tensile test data cover
Externí odkaz:
https://doaj.org/article/726d79f802d84627a2352a84de709526
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4134-4145 (2023)
This paper proposes strain-based failure model of A533B1 pressure vessel steel to simulate failure, followed by application to OECD lower head failure (OLHF) test simulation for experimental validation. The proposed strain-based failure model uses si
Externí odkaz:
https://doaj.org/article/92154ed2de0c48ed9908f2f477acc521
Experimental validation of ASME strain-based seismic assessment methods using piping elbow test data
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1616-1629 (2023)
To quantify the conservatism of existing ASME strain-based evaluation methods for seismic loading, this paper presents very low cycle fatigue test data of elbows under various cyclic loading conditions and comparison of evaluation results with experi
Externí odkaz:
https://doaj.org/article/c8d64def07754141b8c05225cf327a04
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 4, Pp 1250-1264 (2023)
This paper presents approximate in-depth residual stress and plastic strain profiles for laser-peened alloy 600 surface via FE analysis. In approximations, effects of the initial welding residual stress and the number of shots are quantified. Based o
Externí odkaz:
https://doaj.org/article/6611c4c9c45042c3a78e850012406252
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 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