Seismic analysis of a steam generator for Gyeongju and Pohang earthquakes

Authors: Myung Jo Jhung, Youngin Choi, Changsik Oh, Gangsig Shin, Chan Il Park

Source: Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1577-1586 (2023)

Subject Terms: Steam generator, Earthquake, Modal analysis, Seismic analysis, Gyeongju earthquake, Pohang earthquake, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573323000645; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/f14a9c9fab8a450f95649fba2dd95caf

Dynamic response of a fuel assembly for a KSNP design earthquake

Authors: Myung Jo Jhung, Youngin Choi, Changsik Oh

Source: Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3353-3360 (2022)

Subject Terms: Fuel assembly, Earthquake, Modal analysis, Seismic analysis, KSNP Design earthquake, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S173857332200167X; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/a290ed3062a84aad814e7300959027ff

Analytical method to estimate cross-section stress profiles for reactor vessel nozzle corners under internal pressure

Authors: Changsik Oh, Sangmin Lee, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 401-413 (2022)

Subject Terms: Reactor vessel nozzle, Nozzle corner, Stress intensity factor, Stress concentration factor, Finite element analysis, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573321004873; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/f6e6aadb2df74818aad534bc3a0f6b81

Earthquake response of a core shroud for APR1400

Authors: Myung Jo Jhung, Youngin Choi, Chang-Sik Oh

Source: Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2716-2727 (2021)

Subject Terms: Reactor vessel internals (RVI), Core shroud, Finite element model, Seismic analysis, Earthquake, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573321000978; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/108bc19263e64990b5775b65773906fc

Vessel failure sensitivities of an advanced reactor for SBLOCA

Authors: Myung Jo Jhung, Chang-Sik Oh, Youngin Choi, Sung-Sik Kang

Source: Nuclear Engineering and Technology, Vol 52, Iss 1, Pp 185-191 (2020)

Subject Terms: Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573319302931; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/6558a741997f407dab558e6925492c6d

Fluid effect on the modal characteristics of a square tank

Authors: Myung Jo Jhung, Sung-Sik Kang

Source: Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1117-1131 (2019)

Subject Terms: Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573318309082; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/a2341fee3269471da0f0f1d6d158bdad

Korean Round-Robin Tests Result for New International Program to Assess the Reliability of Emerging Nondestructive Techniques

Authors: Kyung Cho Kim, Jin Gyum Kim, Sung Sik Kang, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 49, Iss 3, Pp 651-661 (2017)

Subject Terms: Bottom-mounted Instrumentation, Dissimilar Metal Weld, Nondestructive Techniques, Round-robin Test, Stress Corrosion Cracking, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573316301917; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/27b2f33281a34bd6913c227cb8021b76

Added Mass Estimation of Square Sections Coupled with a Liquid Using Finite Element Method

Authors: Kyeong Hoon Jeong, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 49, Iss 1, Pp 234-244 (2017)

Subject Terms: Added Mass, Finite Element Analysis, Hydroelastic Coupling, Square Section, Submerged Beam, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573316301310; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/37fc580787c0420a8e4867117ec958bb

Probabilistic Fracture Mechanics Analysis of Boling Water Reactor Vessel for Cool-Down and Low Temperature Over-Pressurization Transients

Authors: Jeong Soon Park, Young Hwan Choi, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 545-553 (2016)

Subject Terms: Cool-Down, Low Temperature Over-Pressurization, Probabilistic Fracture Mechanics, Reactor Pressure Vessel, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315002545; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/675b670335534f5e8a3b9eae99ea83ea

Modeling of Reinforced Concrete for Reactor Cavity Analysis under Energetic Steam Explosion Condition

Authors: Seung Hyun Kim, Yoon-Suk Chang, Yong-Jin Cho, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 48, Iss 1, Pp 218-227 (2016)

Subject Terms: Equivalent Homogeneous Concrete Property, Finite Element Analysis, Reactor Cavity, Structural Failure Criteria, Yield Criterion, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315002259; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/ddcf18f134db4819b7aea871b95d8f25

Integrity analysis of an upper guide structure flange

Authors: Ki-Hyoung Lee, Sung-Sik Kang, Myung Jo Jhung

Source: Nuclear Engineering and Technology, Vol 47, Iss 6, Pp 766-775 (2015)

Subject Terms: Design Acceptance Criteria, Elastic Analysis, Reactor Vessel Internals, Seismic Analysis, Structural Analysis, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315001643; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/9efcb9f90898486f851223850f5abc5c

Free vibration analysis of perforated plate with square penetration pattern using equivalent material properties

Authors: Myung Jo Jhung, Kyeong Hoon Jeong

Source: Nuclear Engineering and Technology, Vol 47, Iss 4, Pp 500-511 (2015)

Subject Terms: Effective modulus of elasticity, Finite-element analysis, Ligament efficiency, Natural frequency, Perforated plate, Rayleigh–Ritz method, Square plate, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315000856; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/60931998ea9441e7b5782d7bf4945e8d

EFFECTS OF TEMPERING AND PWHT ON MICROSTRUCTURES AND MECHANICAL PROPERTIES OF SA508 GR.4N STEEL

Authors: KI-HYOUNG LEE, MYUNG JO JHUNG, MIN-CHUL KIM, BONG-SANG LEE

Source: Nuclear Engineering and Technology, Vol 46, Iss 3, Pp 413-422 (2014)

Subject Terms: Reactor Pressure Vessel, Heat Treatment, Tempering, PWHT, Transition Property, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315301376; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/ed13adbd1e1e451cb3c803af0df61379

DEVELOPMENT OF GREEN’S FUNCTION APPROACH CONSIDERING TEMPERATURE-DEPENDENT MATERIAL PROPERTIES AND ITS APPLICATION

Authors: HAN-OK KO, MYUNG JO JHUNG, JAE-BOONG CHOI

Source: Nuclear Engineering and Technology, Vol 46, Iss 1, Pp 101-108 (2014)

Subject Terms: Fatigue Monitoring, Green's Function Approach, Temperature-dependent Material Properties, Thermal Stress Analysis, Weight Factor, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315300954; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/1a2f36793e2b465fa988ddca10980a33

ASSESSMENT OF THERMAL FATIGUE IN MIXING TEE BY FSI ANALYSIS

Authors: MYUNG JO JHUNG

Source: Nuclear Engineering and Technology, Vol 45, Iss 1, Pp 99-106 (2013)

Subject Terms: FSI(Fluid-Structure Interaction) Analysis, Mixing Tee, Thermal Fatigue, Thermal-hydraulic Analysis, Piping System, Turbulent Flow, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315300127; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/a2d2ae4729ce4fd88256fda81b12e1d2

Fuel Assembly Modelling for Dynamic Analysis of Reactor Internals and Core

Authors: Myung Jo Jhung, Jong Keun Hwang, Yeon Seung Kim

Source: JOURNAL- KOREAN NUCLEAR SOCIETY. 27(5):743-743

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCZT003167562&indx=1&recIds=ETOCZT003167562

Root Cause Analysis of SI Nozzle Thermal Sleeve Breakaway Failures Occurring at PWR Plants.

Authors: Jong Chull Jo, Myung Jo Jhung, Seon Oh Yu, Hho Jung Kim, Young Gill Yune

Source: Journal of Pressure Vessel Technology; Feb2009, Vol. 131 Issue 1, p04:1-04:14, 14p, 14 Diagrams, 3 Charts, 21 Graphs

LIFE ESTIMATION OF PWR STEAM GENERATOR U-TUBES SUBJECTED TO FOREIGN OBJECT-INDUCED FRETTING WEAR.

Authors: Jong Chull Jo¹ jcjo@kins.re.kr, Myung Jo Jhung¹, Woong Sik Kim¹, Hho Jung Kim¹

Source: Nuclear Technology. Oct2005, Vol. 152 Issue 1, p118-128. 11p. 6 Diagrams, 5 Charts, 7 Graphs.

Subject Terms: *NUCLEAR reactors, *STEAM generators, *STEAM-turbines, *FLUID dynamics, *FINITE element method, *MATHEMATICAL models