Scholarworks@UNIST

UNIST Library

Browsing by Author : 이덕중

All A B C D E F G H I J K L M N O P Q R S T U V W X Y Z

가 나 다 라 마 바 사 아 자 차 카 타 파 하

Sort by: In order: Results/Page Etal:

Showing results 101 to 120 of 550

Conceptual Core Design of a Small Modular Fast Reactor Cooled by Lead-Bismuth Eutectic

Nguyen, Dong Cao Tung , Choe, Jiwon , Ebiwonjumi, Bamidele , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2018-04-22 View6

Conceptual Design of Inverted Core Lead Bismuth Eutectic Fast Reactor for Marine Applications

Khandaq, Muhammad Farid , Nguyen, Tung Dong Cao , Jeong, Eun , Fynan, Douglas A. , Lee, Deokjung

Conference Paper Issue Date2022-05-16 View8

Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operation File

Jang, Jaerim , Choe, Jiwon , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung , Shin, Ho Cheol

Article Issue Date2020-06 View6

Convergence analysis of coarse mesh finite difference method applied to two-group three-dimensional neutron diffusion problem File

Lee, Deokjung

Article Issue Date2012-09 View13

Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem

Lee, Deokjung , Downar, TJ , Kim, Y

Article Issue Date2004-06 View8

Convergence analysis of two-node CMFD method applied to neutron diffusion eigenvalue problem

Jeong, Yongjun , Park, Jinsu , Lee, Hyun Chul , Lee, Deokjung

Conference Paper Issue Date2015-06-07 View7

Convergence Analysis of Two-Node CMFD Method for TWO-Group Neutron Diffusion Eigenvalue Problem

Jeong, Yongjin , Park, Jinsu , Lee, Hyun Chul , Lee, Deokjung

Conference Paper Issue Date2015-05-06 View7

Convergence analysis of two-node CMFD method for two-group neutron diffusion eigenvalue problem File

Jeong, Yongjin , Park, Jinsu , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2015-12 View5

Coolant Void Reactivity Analysis of CANDU Lattice

Park, Jinsu , Lee, Hyunsuk , Tak, Taewoo , Lee, Deokjung

Conference Paper Issue Date2016-05-12 View8

Core Design of 100MWe Advanced Nitride-fueled Simplified Liquid Metal Cooled Fast Reactor

Nguyen, Tung Dong Cao , Kim, Ji Young , Choe, Jiwon , Bang, In Cheol , Lee, Deokjung

Conference Paper Issue Date2022-04-19 View4

Core design of long-cycle small modular lead-cooled fast reactor File

Tung Dong Cao Nguyen , Choe, Jiwon , Ebiwonjumi, Bamidele , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2019-01 View6

Core Design Study of Ultra-long Cycle Fast Reactor Concept

Lee, Deokjung , None

Conference Paper Issue Date2013 View5

Coupled Fuel Depletion/Thermal Hydraulic Analysis of a Liquid Metal Fast Reactor ANST100e

Tran, Tuan Quoc , Nguyen, Tung Dong Cao , Lee, Deokjung

Conference Paper Issue Date2023-10-25 View8

Coupled Neutronics-Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code System File

Yu, Jiankai , Lee, Hyunsuk , Kim, Hanjoo , Zhang, Peng , Lee, Deokjung

Article Issue Date2020-05 View2

Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system File

Nguyen, Tung Dong Cao , Tran, Tuan Quoc , Lee, Deokjung

Article Issue Date2023-11 View27

Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS File

Yu, Jiankai , Lee, Hyunsuk , Kim, Hanjoo , Zhang, Peng , Lee, Deokjung

Article Issue Date2020-06 View9

Creation of a Database of Uncertainties for ICSBEP Handbook and Tool for Covariance Generation

Jeong, Sanggeol , Hill, Ian , Kikusato, Hiroshi , Lee, Deokjung

Conference Paper Issue Date2017-04-16 View9

Criticality Analysis of VVER-1000 Mock-up with the Monte Carlo code MCS

Setiawan, Fathurrahman , Lemaire, Matthieu , Lee, Hyunsuk , Lee, Deokjung

Conference Paper Issue Date2019-10-25 View3

Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages File

Lee, Hochul , Jang, Jaerim , Jang, Junkyung , Kang, Hyunwook , Kim, Wonkyeong , Lee, Deokjung , Lee, Hyun Chul

Article Issue Date2021-02 View11

Current developments of the pwr core analysis code RAST-K2.0

Zheng, Youpi , Park, Minyong , Lee, Deokjung , Lee, Eunki , Shin, Hochel.

Conference Paper Issue Date2016-04-17 View8

<< < 1 2 3 4 5 6 7 8 9 10 > >>

RSS 1.0 RSS 2.0

UNIST | Library

Tel : 052-217-1404 / Email : scholarworks@unist.ac.kr

ScholarWorks@UNIST was established as an OAK Project for the National Library of Korea.