DSpace at KOASAS
Browsing DSpace

Browse "NE-Conference Papers(학술회의논문)" by Author 문지원

A to Z

All 0-9

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

or enter first few letters:

Showing results 1 to 11 of 11

1
Development of Low-Temperature Fuel Performance Analysis Code for Micro Ultra Long Life Lead-cooled Fast Reactor

문지원; 류호진, 한국원자력학회 2021 온라인 추계학술발표회, 한국원자력학회, 2021-10-22

2
Development of Transient Fuel Performance Analysis System for Ultra Long-Life Micro Lead-Cooled Fast Reactor

문지원; 류호진, 한국원자력학회 2022 춘계학술발표회, 한국원자력학회, 2022-05-19

3
Effects of Neutron Absorbing Nuclide on Criticality of Spent Nuclear Fuel Storage Systems

이태규; 류호진; 문지원, 한국원자력학회 2018 추계학술발표회, 한국원자력학회, 2018-10-25

4
Fabrication and Properties of Metal Matrix Composites as a Neutron Absorber Material of the Spent Fuel Dry Storage System

문지원; 류호진; 이태규, 한국원자력학회 2017 춘계학술대회, 한국원자력학회, 2017-05-18

5
Fuel Performance Analysis of Accident-Tolerant Fuel (ATF) Rod with Multi-Layered Cladding During Load Following Operation

문지원; 김형진; 류호진, 한국원자력학회 2023 추계학술발표회, 한국원자력학회, 2023-10-26

6
Low Linear Power Oxide Fuel Performance Evaluation for Micro Lead-cooled Fast Reactor

문지원; 김형진; Sweidan, Faris; 류호진, 2020 한국원자력학회 온라인 추계학술발표회, 한국원자력학회, 2020-12-18

7
Metallic Fuel Performance Evaluation for Micro Lead cooled Fast Reactor

문지원; 김형진; Sweidan, Faris; 류호진, 2020년도 한국원자력학회 온라인 춘계학술발표회, 한국원자력학회, 2020-07-09

8
Thermal-mechanical Analysis of Lead-cooled Fast Reactor Fuel Assembly with the Inverted Core Design

김형진; 문지원; 류호진, 한국원자력학회 2023 춘계학술발표회, 한국원자력학회, 2023-05-19

9
Thermo-mechanical Analysis of Multi-layered Accident-tolerant fuel (ATF) Claddings

문지원; 류호진, 한국원자력학회 2023 춘계학술발표회, 한국원자력학회, 2023-05-18

10
다층구조 피복관을 포함하는 사고저항성 핵연료 시스템의 다물리 해석

문지원; 류호진, 한국복합재료학회 2022 추계학술대회, 한국복합재료학회, 2022-11-02

11
이종의 강화재 (B4C 입자, Gd2O3 입자)를 포함한 중성자 흡수재용 Al 금속복합재료의 제조와 특성 분석

문지원; 이태규; 류호진, 한국분말야금학회 2018 추계학술대회, 한국분말야금학회, 2018-11-13

Discover

rss_1.0 rss_2.0 atom_1.0