국제학술발표회 논문집
| No | Conference Name | Year | Subject Area | Title | Author | Paper File |
|---|---|---|---|---|---|---|
| 46 | RPHA-2023 | 2023 | Advanced Reactor Core Design | Load-follow Simulation of a 540MWth Soluble-Boron-Free SMR using CSBA | Yunseok Jeong(KAIST), Steven Wijaya(KAIST) and Yonghee Kim(KAIST) | PDF보기 |
| 47 | RPHA-2023 | 2023 | Advanced Reactor Core Design | Preliminary neutronics and thermal analysis of a heat pipe cooled traveling wave reactor with nonuniform radial fuel arrangement | Kunfeng Ma(Shanghai Jiao Tong Univ.) and Po Hu(Shanghai Jiao Tong Univ.) | PDF보기 |
| 48 | RPHA-2023 | 2023 | Advanced Reactor Core Design | Multi-Physics Rodded Depletion of an Uprated Soluble-Boron-Free ATOM Core Design with Mode-Y logic | Steven Wijaya(KAIST), Yunseok Jeong(KAIST), and Yonghee Kim(KAIST) | PDF보기 |
| 49 | RPHA-2023 | 2023 | Reactor Analysis Methods | Coupled Fuel Depletion/Thermal Hydraulic Analysis of a Liquid Metal Fast Reactor ANST-100e | Tuan Tran(UNIST), Tung Nguyen(UNIST), and Deokjung Lee(UNIST) | PDF보기 |
| 50 | RPHA-2023 | 2023 | Reactor Analysis Methods | Multi-Physics Monte Carlo Simulation for a Fuel Pin-Cell with Continuous Temperature and Density | Muhammad Imron(UNIST) and Deokjung Lee(UNIST) | PDF보기 |
| 51 | RPHA-2023 | 2023 | Reactor Analysis Methods | A Comparative Analysis of eXplainable AI Techniques for Nuclear Reactor Core Anomalies | Hanjoo Kim(UNIST), Sang-Rae Moon(Korea Hydro Nuclear Power Co., Ltd.), and Deokjung Lee(UNIST) | PDF보기 |
| 52 | RPHA-2023 | 2023 | Reactor Analysis Methods | Transport calculation for plate-type nuclear reactor with the direct transport code SHARK | Chen Zhao(Nuclear Power Institute of China), Wenbo Zhao(Nuclear Power Institute of China), and Hongbo Zhang(Nuclear Power Institute of China) | PDF보기 |
| 53 | RPHA-2023 | 2023 | Reactor Analysis Methods | Research on Surrogate Models of Space-time Neutron Dynamics with Artificial Neural Networks | Xiaoqi Li(Xi\'an Jiaotong Univ.), Youqi Zheng(Xi\'an Jiaotong Univ.), Xianan Du(Xi\'an Jiaotong Univ.), Yongping Wang(Xi\'an Jiaotong Univ.), Huabei Yin(Xi\'an Jiaotong Univ.), and Bowen Xiao(Xi\'an Jiaotong Univ.) | PDF보기 |
| 54 | RPHA-2023 | 2023 | Reactor Analysis Methods | Pin-cell Homogenization for PWR-Core Pin-by-pin P1 Calculation | Junwei Qin(Xi\'an Jiaotong Univ.) and Yunzhao Li(Xi\'an Jiaotong Univ.) | PDF보기 |
| 55 | RPHA-2023 | 2023 | Reactor Analysis Methods | Investigation of the SP3 method in fast rector physics analysis | Jun-Shuang Fan(Hokkaido Univ.) and Go Chiba(Hokkaido Univ.) | PDF보기 |
| 56 | RPHA-2023 | 2023 | Reactor Analysis Methods | 2D Neutron Diffusion Calculation Based on Local/Global Iterations Using Proper Orthogonal Decomposition | Masato Ito(Nagoya Univ.), Tomohiro Endo(Nagoya Univ.), Akio Yamamoto(Nagoya Univ.), Taiti Takeishi(Nuclear Fuel Industries:CMA: Ltd.), Yasuhiro Kodama(Nuclear Fuel Industries:CMA: Ltd.), and Hiroaki Nagano(Nuclear Fuel Industries:CMA: Ltd.) | PDF보기 |
| 57 | RPHA-2023 | 2023 | Reactor Analysis Methods | Consistent Variational Nodal Diffusion Method Embedded in Method of Characteristics | Kyung Min Kim(Seoul National Univ.), Han Gyu Lee(Seoul National Univ.), and Hyung Jin Shim(Seoul National Univ.) | PDF보기 |
| 58 | RPHA-2023 | 2023 | Computational Methods & Reactor Analysis | Development of GPU Based Depletion Module by CRAM | Woo Kyoung Ko(Department of Nuclear Engineering:CMA: Seoul National Univ.) and Hyung Jin Shim(Department of Nuclear Engineering:CMA: Seoul National Univ.) | PDF보기 |
| 59 | RPHA-2023 | 2023 | Computational Methods & Reactor Analysis | Deep learning surrogate model for fuel performance analysis | Awais Zahur(UNIST), Muhammad Rizwan Ali(UNIST), Jimin Lee(UNIST), and Deokjung Lee(UNIST) | PDF보기 |
| 60 | RPHA-2023 | 2023 | Computational Methods & Reactor Analysis | Evaluation of Thermal Expansion Reactivity Feedback Effect in Water-moderated Fuel-particle-dispersion System | Kodai Fukuda(Japan Atomic Energy Agency) | PDF보기 |
Last Modified : 2023.11.20
