학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

국제학술발표회 논문집

No Conference Name Year Subject Area Title Author Paper File
496 ISOFIC 2017 MMIS & Remote Control Equipment Testing for Severe Accident Conditions V?t PLA?EK(?JV ?e?), Zuzana KONE?N?(Czech Technical University) PDF보기
497 ISOFIC 2017 MMIS & Remote Control The Design and Implementation of Refuelling Machine Simulator Control System Based on FPGA Zhijun HE, Peng ZHANG(China Nuclear Power Engineering) PDF보기
498 ISOFIC 2017 MMIS & Remote Control Autonomous Algorithm for Safety Function State of Nuclear Power Plant by Using LSTM Daeil LEE, Jonghyun KIM(CSU) PDF보기
499 ISOFIC 2017 MMIS & Remote Control VHDL Verification of FPGA based ESF-CCS for Nuclear Power Plant I&C System Restu MAERANI, Jae Cheon JUNG(KINGS) PDF보기
500 ISOFIC 2017 MMIS & Remote Control FBDScenaGen+: GA-based High-Quality Scenario Generator for FBD Simulation Eui-Sub Kim, Sejin Jung, Junbeom Yoo(KU), Young Jun Lee, Jang Soo Lee(KAERI) PDF보기
501 ISOFIC 2017 MMIS & Remote Control Integrated Human and Organizational Factors oriented Design and Development Method Nicolas HENRY, Renaud AUBIN(EdF) PDF보기
502 RPHA 2015 Design Analyses of Innovative Reactors Preliminary Analysis of New Secondary Shutdown System of Small Modular Pressurized Water Reactor Jiwon Choe, Chidong Kong, Sooyoung Choi, Minyong Park, Deokjung Lee (UNIST), Ho Cheol Shin (KHNP) PDF보기
503 RPHA 2015 Monte Carlo Methods and Applications Hybrid Depletion Method for Monte Carlo Analysis of PWRs Yongjin Jeong, Sooyoung Choi, Hyunsuk Lee, Deokjung Lee (UNIST), Kyoon-Ho Cha, Sun-Kwan Hong (KHNP) PDF보기
504 RPHA 2015 Design Analyses of Innovative Reactors A Comparative Physics Study of New Ultra-Long-Life Sodium-Cooled Cores using Uranium and Thorium Fuels HaeLee Hyun, Ser Gi Hong (KHU) PDF보기
505 RPHA 2015 Design Analyses of Innovative Reactors Nuclear Design for Series Lead Based Reactors in China Yican Wu, Minghuang Wang, Qi Yang, Chao Liu, Bo Chang, Chao Lian, Jieqiong Jiang, FDS Team (CAS) PDF보기
506 RPHA 2015 Reactor Experiments Development of High Intensity D-T Fusion NEutron Generator (HINEG) Jieqiong Jiang PDF보기
507 RPHA 2015 Reactor Analysis Methods Development of Hexagonal Nodal Diffusion Codes at National Tsing-Hua University Jui-Yu Wang, Tzung-Yi Lin, Chih-Wei Chang, Abderrafi M. Ougouag, Yen-Wan Hsueh Liu, Rong-Jiun Sheu (NTHU) PDF보기
508 RPHA 2015 Monte Carlo Methods and Applications MCNP5 Core Calculations Coupled with a Simplified Thermal-Hydraulic Model for GTHTR300 Chia-Chun Tsai, Ju-Ching Sun, Jui-Yu Wang, Yen Wan Hsueh Liu, Rong Jiun Sheu, Yang Chien Tien (NTHU) PDF보기
509 RPHA 2015 Reactor Physics Education Education and Research on Reactor Physics at NTHU in Taiwan Rong-Jiun Sheu, Jui-Yu Wang, Yen-Wan Hsueh Liu (NTHU) PDF보기
510 RPHA 2015 Reactor Physics Education Reactor Physics Education and Research at Nuclear Engineering Department of Seoul National University Hyung Jin Shim, Han Gyu Joo (SNU) PDF보기
Last Modified : 2019.11.27