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Dive into the research topics where Youn-Myoung Lee is active.

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Featured researches published by Youn-Myoung Lee.


Annals of Nuclear Energy | 1995

Nuclide transport of decay chain in the fractured rock medium: A model using continuous time Markov process

Youn-Myoung Lee; Kun Jai Lee

Abstract A model using continuous time Markov process for nuclide transport of decay chain of arbitrary length in the fractured rock medium has been developed. Considering the fracture in the rock matrix as a finite number of compartments, the transition probability for nuclide from the transition intensity between and out of the compartments is represented utilizing Chapman-Kolmogorov equation, with which the expectation and the variance of nuclide distribution for the fractured rock medium could be obtained. A comparison between continuous time Markov process model and available analytical solutions for the nuclide transport of three decay chains without rock matrix diffusion has been made showing comparatively good agreement. Fittings with experimental breakthrough curves obtained with nonsorbing materials such as NaLS and uranine in the artificial fractured rock are also made.


Progress in Nuclear Energy | 2001

A visual environment for system analysis codes

Kyungsu Kim; Jongtae Jeong; S.Y. Mo; Youn-Myoung Lee; C.B. Lee

Abstract A visual environment for system analysis codes (hereinafter called “ViSA”) has been developed to support code users in their input preparations, code executions, and output interpretations. ViSA provides a more convenient way for base input data generation and modification on a user-friendly basis. It also provides on-line graphical displays to give an in-depth understanding of transient thermal-hydraulic behaviors in nuclear power plants. This paper presents the main features of ViSA.


Progress in Nuclear Energy | 2009

A GoldSim model for the safety assessment of an HLW repository

Youn-Myoung Lee; Yong-Soo Hwang


Annals of Nuclear Energy | 2007

Nuclide release from an HLW repository: Development of a compartment model

Youn-Myoung Lee; Chul-Hyung Kang; Yong-Soo Hwang


Progress in Nuclear Energy | 2011

Evaluation of nuclide release scenarios for a hypothetical LILW repository

Youn-Myoung Lee; Jongtae Jeong


Progress in Nuclear Energy | 2013

An evaluation of an earthquake scenario for a pyroprocessed waste repository

Youn-Myoung Lee; Jongtae Jeong; Jong-Won Choi


Journal of the Nuclear Fuel Cycle and Waste Technology | 2012

Production and Application of Domestic Input Data for Safety Assessment of Disposal

Chung-Kyun Park; Jae-Kwang Lee; Min-Hoon Baik; Youn-Myoung Lee; Nak-Youl Ko; Jongtae Jeong


Journal of the Nuclear Fuel Cycle and Waste Technology | 2013

A-KRS GoldSim Model Verification: A Comparison Study of Performance Assessment Model

Youn-Myoung Lee; Jongtae Jeong


Progress in Nuclear Energy | 2016

A preliminary comparison study of two options for disposal of high-level waste

Youn-Myoung Lee; Heui-Joo Choi; Kyungsu Kim


Journal of the Nuclear Fuel Cycle and Waste Technology | 2012

A Probabilistic Safety Assessment of a Pyro-processed Waste Repository

Youn-Myoung Lee; Jongtae Jeong

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