DYNAMIC MODELING AND ANALYSIS OF ALTERNATIVE FUEL CYCLE SCENARIOS IN KOREA

CHANG JOON JEON

Nuclear Engineering and Technology

2007 .01

A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

MASAKAZU ICHIMIYA

Nuclear Engineering and Technology

2007 .01

FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS

W. S. YANG

Nuclear Engineering and Technology

2012 .01

Fabrication of Metal Fuel Rodlets for Sodium-cooled Fast Reactor

Ki-Hwan Kim ,  Seok-Jin Oh ,  Soo-Sung Kim 외 2명

대한용접학회 특별강연 및 학술발표대회 개요집

2012 .05

TECHNICAL RATIONALE FOR METAL FUEL IN FAST REACTORS

YOON IL CHANG

Nuclear Engineering and Technology

2007 .01

금속연료를 사용하는 소듐냉각 고속로의 안전특성

정해용

에너지공학

2014 .12

FAST REACTOR TECHNOLOGY R&D ACTIVITIES IN CHINA

XU MI

Nuclear Engineering and Technology

2007 .01

ELECTROCHEMICAL PROCESSING OF USED NUCLEAR FUEL

K. M. GOFF ,  J. C. WASS ,  K. C. MARSDEN 외 1명

Nuclear Engineering and Technology

2011 .01

Development and Validation of a Nuclear Fuel Cycle Analysis Tool: A Future Code

S. K. Kim ,  W. I. Ko ,  이윤희

Nuclear Engineering and Technology

2013 .01

Dynamic Modeling of the Korean Nuclear Euel Cycle

Jeong ,  Chang-Joon ,  Pa 외 5명

한국방사성폐기물학회 학술대회

2004 .01

Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor

이찬복

Nuclear Engineering and Technology

2016 .01

Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit

Se ,  gey Pe ,  evoznikov

Nuclear Engineering and Technology

2016 .01

An Integrated Multicriteria Decision-Making Approach for Evaluating Nuclear Fuel Cycle Systems for Long-term Sustainability on the Basis of an Equilibrium Model: Technique for Order of Preference by Similarity to Ideal Solution, Preference Ranking Organization Method for Enrichment Evaluation, and Multiattribute Utility Theory Combined with Analytic Hierarchy Process

윤새롬 ,  최성열 ,  고원일

Nuclear Engineering and Technology

2017 .01

소듐 고속로 연료집합체 내부의 열유동 수치해석

이공희 ,  신안동

한국유체기계학회 학술대회 논문집

2017 .12

Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)

Yeo ,  Sunghwan ,  Yeon 외 3명

한국방사성폐기물학회 학술대회

2017 .01

FRENCH PROGRAM TOWARDS AN INNOVATIVE SODIUM COOLED FAST REACTOR

PH. MARTIN

Nuclear Engineering and Technology

2007 .01

Impact of Multi-dimensional Core Thermal-hydraulics on Inherent Safety of Sodium-Cooled Fast Reactor

Young-Min KWON ,  Hae-Yong JEONG ,  Kwi-Seok HA

대한기계학회 춘추학술대회

2008 .11

Sensitivity Analysis of Fabrication Parameters for Dry Process Fuel Performance Using Monte Carlo Simulations

박장제 ,  송기찬 ,  양명승

Nuclear Engineering and Technology

2004 .01

The Investigation of Burnup Characteristics Using the Serpent Monte Carlo Code for a Sodium Cooled Fast Reactor

MEHMET E. KORKMAZ ,  OSMAN AGAR

Nuclear Engineering and Technology

2014 .01

Seismic modeling and analysis for sodium-cooled fast reactor

Koo ,  Gyeong-Hoi ,  Kim 외 3명

Structural engineering and mechanics : An international journal

2012 .01