Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 이성민

Showing results 1 to 9 of 9

1
(A) study of the behavior of the floating absorber for safety at transient (FAST) to improve inherent safety of a sodium-cooled fast reactor and multi-assembly-based design optimization = 고속로 고유 안전성 향상을 위한 피동안전흡수체의 거동 연구 및 다중 어셈블리 기반 설계 최적화link

Lee, Seongmin; Jeong, Yong Hoon; et al, 한국과학기술원, 2022

2
Analysis for the Heat Pipes Failure in a Hybrid Micro Modular Reactor

이성민; 최영재; 정용훈, 2020 한국원자력학회 춘계학술발표회, 한국원자력학회, 2020-07-09

3
Code Validation for the Behavior of Floating Absorber for Safety at Transient (FAST) under the Constant Density Condition

이성민; 정용훈, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-18

4
Conceptual study of Fsat-Spectrum Molten Salt Reactor combined with Energy Storage System

최재진; 이성민; 정용훈, 2021 한국원자력학회 추계학술발표회, 한국원자력학회, 2021-10-21

5
Decontamination Factor Prediction Using Artificial Neural Networks Method

이성민; 정용훈, 2019 한국원자력학회 춘계학술발표회, 한국원자력학회, 2019-05-24

6
Design and analysis of safety system using heat pipe of hybrid micro modular reactor (H-MMR)

최영재; 이성민; 정용훈, 2020 한국원자력학회 춘계학술발표회, 한국원자력학회, 2020-07-09

7
Development of analysis code for behavior of passive safety device in innovative sodium-cooled fast reactor = 혁신소듐냉각로의 피동안전장치 거동 해석 코드 개발link

Lee, Seongmin; Yong Hoon Jeong; et al, 한국과학기술원, 2018

8
Investigation of various floating absorber for safety at transient (FAST) designs

이성민; 정용훈, 2021 한국원자력학회 추계학술발표회, 한국원자력학회, 2021-10-22

9
피동 안전 장치 및 핵연료 집합체

정용훈; 이성민

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