학회지 NET 제47권 3호 (Volume 47., Number 3., April 2015)가 발행되었습니다.

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1. Science Direct 바로가기 :

 http://www.sciencedirect.com/science/journal/17385733/47/3 

2. 원자력학회 홈페이지 바로가기 (창간호부터 신규호까지 게시) : http://www.kns.org/sub/04/sub_04_02.php?search=vol&key=47

 

-Contents- 

 

‘‘Sodium-cooled Fast Reactor Safety and Operating Experiences’’

Invited Articles

A Review of Inherent Safety Characteristics of Metal Alloy Sodium-Cooled Fast Reactor Fuel Against Postulated Accidents

Tanju Sofu 

A Preliminary Evaluation of Unprotected Loss-of-Flow Accident for a Prototype Fast-Breeder Reactor

Tohru Suzuki , Yoshiharu Tobita , Kenichi Kawada , Hirotaka Tagami , Joji Sogabe , Kenichi Matsuba , Kei Ito and Hiroyuki Ohshima 

Prolongation of the BOR-60 Reactor Operation

Alexey l. Izhutov , YURI M. Krasheninnikov , Igor Y. Zhemkov , Artem V. Varivtsev , Yuri V. Naboishchikov ,

Victor S. Neustroev and Valentin K. Shamardin 

Safety Aspects of Intermediate Heat Transport and Decay Heat Removal Systems of Sodium-Cooled Fast Reactors

Subhash Chander Chetal 

Original Articles

Thermal Hydraulics

Quantitative Observation of Co-Current Stratifi ed Two-Phase Flow in a Horizontal Rectangular Channel

Seungtae Lee , Dong-Jin Euh , Seok Kim and Chul-Hwa Song 

Computational Fluid Dynamics Analysis of the Canadian Deuterium Uranium Moderator Tests at the Stern Laboratories Inc.

Hyoung Tae Kim and Se-Myong Chang 

Feasibility Study of a Dedicated Nuclear Desalination System: Low-Pressure Inherent Heat Sink Nuclear Desalination Plant (Lind)

Ho Sik Kim , Hee Cheon NO , YuGwon Jo , Andhika Feri Wibisono , Byung Ha Park , Jinyoung Choi , Jeong Ik Lee , Yong Hoon Jeong and Nam Zin Cho

Nuclear Fuel Cycle and Radioactive Waste Management

Nuclear Fuel Cycle Cost Estimation and Sensitivity Analysis of Unit Costs on the Basis of an Equilibrium Model

S.K. Kim , W.I. Ko , S.R. Youn and R.X. Gao 

Comparison of Neutronic Behavior of Uo 2 , (Th- 233 U)O 2 and (Th- 235 U)O 2 Fuels in a Typical Heavy Water Reactor

Seyed Mohammad Mirvakili , Masoomeh Alizadeh Kavafshary and Atiyeh Joze Vaziri 

Nuclear Fuel and Reactor Materials

Effects of Ion Irradiation on Microstructure and Properties of Zirconium Alloys — A Review

Chunguang Yan , Rongshan Wang , Yanli Wang , Xitao Wang and Guanghai Bai 

Nuclear Structural Analysis and Plant Management & Maintenance

Estimation of Leak Rate Through Circumferential Cracks in Pipes in Nuclear Power Plants

Jai Hak Park , Young Ki Cho , Sun Hye Kim and Jin Ho Lee 

 

Strain-based Plastic Instability Acceptance Criteria for Ferritic Steel Safety Class 1 Nuclear Components Under Level D Service Loads

Ji-Su Kim , Han-Sang Lee , Jong-Sung Kim , Yun-Jae Kim and Jin-Won Kim 

Structural Assessment of Reactor Pressure Vessel Under Multi-Layered Corium Formation Conditions

Tae Hyun Kim , Seung Hyun Kim and Yoon-Suk Chang 

Human Resource Development and Energy Economics & Policy

Construction Schedule Delay Risk Assessment by Using Combined Ahp-Rii Methodology for an International Npp Project

Muhammed Mufazzal Hossen , Sunkoo Kang and Jonghyun Kim 

Technical Note

Nuclear Fuel Cycle and Radioactive Waste Management

Design Optimization of Radiation Shielding Structure for Lead Slowing-Down Spectrometer System

Jeong Dong Kim , Sangjoon Ahn , Yong Deok Lee and Chang Je