Korean science and technology in perspective

von Park, Ik-Soo
Veröffentlicht in Koreana quarterly (1971)

PVP2004-2842 Degradation Estimation of 2.25CR-1Mo Steel by Barkhausen Noise Method

von Cho, Youn-Ho
Veröffentlicht in Recent advances in nondestructive evaluation techniques for material science and industries (2004)

PVP2004-2807 Time Frequency Domain Analysis of the Dispersion of Guided Wave Modes

von Cho, Youn-Ho
Veröffentlicht in Recent advances in nondestructive evaluation techniques for material science and industries (2004)

Multi-Objective Optimization of Arbitrary Supersonic Intake Based on Axiomatic Design Theory Using Kriging/MOGA

von Sandhu, Jatinder Pal Singh
Veröffentlicht in AIAA Aviation Forum (2023 : San Diego, Calif.; Online) Inlets, nozzles, and propulsion systems integration (2023)

Investigation of Flow Phenomena in the Optimization of Supersonic Intake Design with a RANS Solver

von Sandhu, Jatinder Pal Singh
Veröffentlicht in AIAA International Space Planes and Hypersonic Systems and Technologies Conference (25. : 2023 : Bangalore) 25th AIAA International Space Planes and Hypersonic Systems and Technologies Conference 2023 ; Volume 1 of 2 (2023)

UNCONVENTIONAL APPROACH SIMPLIFIES STEEL CATENARY RISER DECOMMISSIONING

von Orr, Ansel
Veröffentlicht in Offshore Technology Conference (2021 : Houston, Tex.) Offshore Technology Conference (OTC 2021) ; Volume 6 of 6 (2021)

Development of a Thermal Hydraulics Code for a Transient Two-Phase Flow Analysis in PWR Steam Generators

von Yoon, Han Young
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

A Three-Dimensional PWR LBLOCA Simulation Using the CUPID Code

von Park, Ik Kyu
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

A Three-Dimensional Multi-Physics Analysis of the Steam Line Break Accident of a PWR Using CUPID-RV/MASTER

von Lee, Jae Ryong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)

Multi-Scale and Multi-Physics Nuclear Reactor Simulation for the Next Generation LWR Safety Analysis

von Yoon, Han Young
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9 (2020)