E-LIB Suche - Ergebnisse für: Eoh, Jaehyuk

1

Design and safety features of SALUS-100: A long fuel-cycled..:

Eoh, Jaehyuk ; Park, Chang-Gyu ; Lim, Jae-Yong...
Nuclear Engineering and Design. 420 (2024) - p. 112996 , 2024

Link: https://doi.org/10.1016/..

2

Heat Transfer Performance Tests of a Circular-Fin Sodium-to..:

Lee, Jewhan ; Kim, Dehee ; Eoh, Jaehyuk..
International Journal of Energy Research. 2024 (2024) - p. 1-11 , 2024

Link: https://doi.org/10.1155/..

3

Validation of GAMMA+ code for SFR application using FFTF lo..:

Hong, Jonggan ; Tak, Nam-il ; Sik Lim, Hong.
Nuclear Engineering and Design. 417 (2024) - p. 112816 , 2024

Link: https://doi.org/10.1016/..

4

High-temperature material properties of type 316L stainless..:

Lee, Hyeong-Yeon ; Nam, Ki-Ean ; Eoh, Jaehyuk
Nuclear Engineering and Technology. , 2024

Link: https://doi.org/10.1016/..

5

Similarity evaluation of the pump simulation loop in STELLA..:

Yoon, Jung ; Lee, Jewhan ; Eoh, Jaehyuk..
Nuclear Engineering and Technology. 55 (2023) 1 - p. 353-363 , 2023

Link: https://doi.org/10.1016/..

6

Design of type 316L stainless steel 700 °C high-temperature..:

Lee, Hyeong-Yeon ; Kim, Hyeonil ; Eoh, Jaehyuk
Nuclear Engineering and Technology. 55 (2023) 10 - p. 3581-3590 , 2023

Link: https://doi.org/10.1016/..

7

Heat transfer system design of sodium test facility STELLA-:

Lee, Jewhan ; Eoh, Jaehyuk ; Yoon, Jung..
Annals of Nuclear Energy. 191 (2023) - p. 109930 , 2023

Link: https://doi.org/10.1016/..

8

Design and Thermal-Hydraulic Evaluation of Integrated Steam..:

Kim, Namhyeong ; Yoon, Jung ; Eoh, Jaehyuk...
International Journal of Energy Research. 2023 (2023) - p. 1-20 , 2023

Link: https://doi.org/10.1155/..

9

Design of large-scale sodium thermal-hydraulic integral eff..:

Lee, Jewhan ; Eoh, Jaehyuk ; Yoon, Jung..
Nuclear Engineering and Technology. 54 (2022) 9 - p. 3551-3566 , 2022

Link: https://doi.org/10.1016/..

10

Improvement of GAMMA+ code for system transient and thermo-..:

Tak, Nam-il ; Sik Lim, Hong ; Hong, Jonggan...
Nuclear Engineering and Design. 399 (2022) - p. 112002 , 2022

Link: https://doi.org/10.1016/..

11

Performance test and uncertainty analysis of the FBG-based ..:

KIM, Byeong-Yeon ; LEE, Jewhan ; CHO, Youngil..
Nuclear Engineering and Technology. 54 (2022) 12 - p. 4412-4421 , 2022

Link: https://doi.org/10.1016/..

12

Securing integrity of high-temperature pressure boundary co..:

Lee, Hyeong-Yeon ; Eoh, Jaehyuk
International Journal of Pressure Vessels and Piping. 195 (2022) - p. 104598 , 2022

Link: https://doi.org/10.1016/..

13

Performance and size comparison of two-stage and three-stag..:

Choi, Jae Hyun ; Yoon, Jung ; Eoh, Jaehyuk..
Nuclear Engineering and Design. 380 (2021) - p. 111309 , 2021

Link: https://doi.org/10.1016/..

14

Study on convective heat transfer correlations for sodium-t..:

Hong, Jonggan ; Lee, Jewhan ; Eoh, Jaehyuk
Nuclear Engineering and Design. 371 (2021) - p. 110963 , 2021

Link: https://doi.org/10.1016/..

15

Heat transfer characteristics of redan structure in large-s..:

Yoon, Jung ; Lee, Jewhan ; Kim, Hyungmo..
Nuclear Engineering and Technology. 53 (2021) 4 - p. 1109-1118 , 2021

Link: https://doi.org/10.1016/..