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Numerical simulation of a toroidal single-phase natural circulation loop with a k-k-ω transitional turbulence model
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Numerical simulation of a toroidal single-phase natural circulation loop with a k-k-ω transitional turbulence model

Geng, Yiwa ; Liu, Xiongbin ; Li, Xiaotian ; Zhang, Yajun

Nuclear Engineering and Technology, 2024, 56(1), , pp.233-240 [Periódico revisado por pares]

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Application of CFD model for Passive Autocatalytic Recombiners to formulate an empirical correlation for integratral containment analysis
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Application of CFD model for Passive Autocatalytic Recombiners to formulate an empirical correlation for integratral containment analysis

Shukla Vikram ; Gera Bhuvaneshwar ; Ganju Sunil ; Varma Salil ; Maheshwari N.K. ; Guchhait P.K. ; Sengupta S.

Nuclear Engineering and Technology, 2022, 54(11), , pp.4159-4169 [Periódico revisado por pares]

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Thickness evaluation of Cr coating fuel rod using encircle ECT sensor
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Thickness evaluation of Cr coating fuel rod using encircle ECT sensor

박정원 ; 하종문 ; 승홍민 ; 장훈(한전원자력연료 ; 최원재

Nuclear Engineering and Technology, 2022, 54(9), , pp.3272-3282 [Periódico revisado por pares]

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Evaluation of cadmium ratio for conceptual design of a cyclotronbased thermal neutron radiography system
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Evaluation of cadmium ratio for conceptual design of a cyclotronbased thermal neutron radiography system

Weng-Sheng Kuo

Nuclear Engineering and Technology, 2022, 54(7), , pp.2572-2578 [Periódico revisado por pares]

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An improved regularized particle fi lter for remaining useful life prediction in nuclear plant electric gate valves
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An improved regularized particle fi lter for remaining useful life prediction in nuclear plant electric gate valves

Ren-yi Xu ; Hang Wang ; Min-jun Peng ; Yong-kuo Liu

Nuclear Engineering and Technology, 2022, 54(6), , pp.2107-2119 [Periódico revisado por pares]

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6
Conceptual design of a copper-bonded steam generator for SFR and the development of its thermalhydraulic analyzing code
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Conceptual design of a copper-bonded steam generator for SFR and the development of its thermalhydraulic analyzing code

임성혁 ; 정요한 ; 홍종간 ; 최선락

Nuclear Engineering and Technology, 2022, 54(6), , pp.2262-2275 [Periódico revisado por pares]

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7
Physical protection system vulnerability assessment of a small nuclear research reactor due to TNTshaped charge impact on its reinforced concrete wall
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Physical protection system vulnerability assessment of a small nuclear research reactor due to TNTshaped charge impact on its reinforced concrete wall

무지훈 ; Sunil S. Chirayath ; 조성국(이노스기술

Nuclear Engineering and Technology, 2022, 54(6), , pp.2135-2146 [Periódico revisado por pares]

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8
Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation
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Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation

Xiaoyu Li ; Chuhao Li ; Yang Hu ; Yongqi Yu ; Wenjie Zeng ; Haibiao Wu

Nuclear Engineering and Technology, 2022, 54(6), , pp.2048-2054 [Periódico revisado por pares]

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9
Corrosion behavior and mechanism of CLAM and 316L steels in fl owing Pb – 17Li alloy under magnetic field
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Corrosion behavior and mechanism of CLAM and 316L steels in fl owing Pb – 17Li alloy under magnetic field

Zunqi Xiao ; Jing Liu ; Zhizhong Jiang ; Lin Luo ; Qunying Huang

Nuclear Engineering and Technology, 2022, 54(6), , pp.1962-1971 [Periódico revisado por pares]

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Graded approach to determine the frequency and diffi culty of safety culture attributes: The F-D matrix
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Graded approach to determine the frequency and diffi culty of safety culture attributes: The F-D matrix

안지예 ; 민병주 ; 이승준

Nuclear Engineering and Technology, 2022, 54(6), , pp.2067-2076 [Periódico revisado por pares]

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