eISSN : 2234-358X
pISSN : 1738-5733
Journal Information  l  e-Submission  l  View-FullText
Journal Information > Introduction
 
 Vol.46 No.6 December 2014
 (name, affiliation, e-mail id).
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), bimonthly publishes articles related to the theory and application of nuclear science and technology
The NET publishes original research and review papers and technical notes in English. All submitted papers and technical notes will be reviewed for technical content.
It is understood that the paper has been neither published nor currently submitted for publication elsewhere. The copyright of all published papers and notes will be vested in KNS. No article can be published unless accompanied by a signed publication agreement which specifies a transfer of copyright from authors to KNS and author responsibility for protecting proprietary and third-party rights.
Also, a manuscript should be submitted electronically with recommendation of over 5 reviewers (name, affiliation, e-mail id).

Issue Paper
725 INTEGRATED DIAGNOSTIC TECHNIQUE FOR NUCLEAR POWER PLANTS
  Diagnosis; Hybrid Diagnostic System; Information Integration; Subsystem; Fast Breeder Reactor;
  Gofuku, Akio
737 APPLICATION OF MONITORING, DIAGNOSIS, AND PROGNOSIS IN THERMAL PERFORMANCE ANALYSIS FOR NUCLEAR POWER PLANTS
  Thermal Efficiency; In-situ Analysis; Condition-Based Maintenance; Turbine Cycle; Nuclear Power Plant
  Kim, Hyeonmin;Na, Man Gyun;Heo, Gyunyoung
753 FUNCTIONAL MODELLING FOR FAULT DIAGNOSIS AND ITS APPLICATION FOR NPP
  Fault Diagnosis; Model Based Reasoning; Artificial Intelligence; Decision Support
  Lind, Morten;Zhang, Xinxin;
773 INCORPORATING PRIOR BELIEF IN THE GENERAL PATH MODEL: A COMPARISON OF INFORMATION SOURCES
  General Path Model; Bayesian Updating; Type III Prognostics;
  Coble, Jamie;Hines, J. W esley
783 COARSE MESH FINITE DIFFERENCE ACCELERATION OF DISCRETE ORDINATE NEUTRON TRANSPORT CALCULATION EMPLOYING DISCONTINUOUS FINITE ELEMENT METHOD
  DFEM; Sn Method; Source Convergence Acceleration; General Geometry Application; Partial Current Based CMFD
  Lee, Dong Wook;Joo, Han Gyu;
797 THERMAL HYDRAULIC ISSUES OF CONTAINMENT FILTERED VENTING SYSTEM FOR A LONG OPERATING TIME
  Containment Filtered Venting System (CFVS); Severe Accident; Depressurization; Thermal Hydraulic;
  Na, Young Su;Ha, Kwang Soon;Park, Rae-Joon;Park, Jong-Hwa;Cho, Song-Won;
803 OBSERVABILITY-IN-DEPTH: AN ESSENTIAL COMPLEMENT TO THE DEFENSE-IN-DEPTH SAFETY STRATEGY IN THE NUCLEAR INDUSTRY
  Keyword Observability-in-depth; Accident Pathogen; Latent Failure; Defense-in-depth; Safety Blind Spot ;
  Favaro, Francesca M.;Saleh, Joseph H.;
817 INVESTIGATION ON EFFECTS OF ENLARGED PIPE RUPTURE SIZE AND AIR PENETRATION TIMING IN REAL-SCALE EXPERIMENT OF SIPHON BREAKER
  Siphon Breaker; Air Sweep-out; Pipe Rupture Accident; Research Reactor ;
  Kang, Soon Ho;Lee, Kwon-Yeong;Lee, Gi Cheol;Kim, Seong Hoon;Chi, Dae Young;Seo, Kyoungwoo;Yoon, Juhyeon;Kim, Moo Hwan;Park, Hyun Sun;
825 DEVELOPMENT AND VALIDATION OF THE AEROSOL TRANSPORT MODULE GAMMA-FP FOR EVALUATING RADIOACTIVE FISSION PRODUCT SOURCE TERMS IN A VHTR
  VHTR; Fission Product; Aerosol; Transport; Deposition; MAEROS;
  Yoon, Churl;Lim, Hong Sik;
837 DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAY
  Fissile Assay; Slowing Down; Neutron Source; Fuel Cycle; Nuclearaterial Utilization; Resolution; Radiation Measurement;
  Lee, YongDeok;Park, Chang Je;Ahn, Sang Joon;Kim, Ho-Dong;
847 A STUDY ON ADSORPTION AND DESORPTION BEHAVIORS OF 14C FROM A MIXED BED RESIN
  Ion-exchange Equilibrium; Adsorption and Desorption; Spent resin; $^{14}C$ 수식 이미지 Radionuclide; Radioactive Waste Disposal; Stripping Solution;
  Park, Seung-Chul;Cho, Hang-Rae;Lee, Ji-Hoon;Yang, Ho-Yeon;Yang, O-Bong;
857 INFLUENCE OF MECHANICAL ALLOYING ATMOSPHERES ON THE MICROSTRUCTURES AND MECHANICAL PROPERTIES OF 15Cr ODS STEELS
  Oxide Dispersion Strengthened Steel; Mechanical Alloying Atmosphere; Oxygen Concentration; Oxide Particle; Creep Strength;
  Noh, Sanghoon;Choi, Byoung-Kwon;Kang, Suk Hoon;Kim, Tae Kyu;
863 ESTIMATIONS OF HEAT CAPACITIES FOR ACTINIDE DIOXIDE: UO2, NpO2, ThO2, AND PuO2
  Nuclear Fuels; Minor Actinide; Temperature Dependence; Uranium Dioxide; Debye Functions ;
  Eser, E.;Koc, H.;Gokbulut, M.;Gursoy, G.;
869 DETECTION OF ODSCC IN SG TUBES DEPENDING ON THE SIZE OF THE CRACK AND ON THE PRESENCE OF SLUDGE DEPOSITS
  Steam Generator; Alloy 600 Mill Annealed Tube; Outside Diameter Stress Corrosion Cracking; Eddy Current Inspection; Probability of Detection; Steam Generator Chemical Cleaning; Sludge Deposit;
  Chung, Hansub;Kim, Hong-Deok;Kang, Yong-Seok;Lee, Jae-Gon;Nam, Minwoo;
875 CURRENT STATUS OF INTEGRITY ASSESSMENT BY SIPPING SYSTEM OF SPENT FUEL BUNDLES IRRADIATED IN CANDU REACTOR
  Sipping System; CANDU Reactor; Integrity Assessment; Defective Fuel bundle;
  Park, Jong-Youl;Shim, Moon-Soo;Lee, Jong-Hyeon;
883 INFLUENCE OF SIGNAL-TO-NOISE RATIO ON EDDY CURRENT SIGNALS OF CRACKS IN STEAM GENERATOR TUBES
  Signal-to-Noise Ratio; Detectability; Sizing Accuracy; Eddy Current Test; Stress Corrosion Crack;
  Hur, Do Haeng;Choi, Myung Sik;Shim, Hee-Sang;Lee, Deok Hyun;Yoo, One;