The Proceedings of the International Conference on Nuclear Engineering (ICONE)

The Proceedings of the International Conference on Nuclear Engineering (ICONE) is …
instance of (P31):
conference proceedings seriesQ27785883

External links are
P8375Crossref journal ID308059
P236ISSN2424-2934
P7363ISSN-L2424-2934
P11504J-STAGE journal IDjsmeicone
jsmeicone
P10283OpenAlex IDS4210234662

P495country of originJapanQ17
P407language of work or nameEnglishQ1860
P1476titleProceedings of the International Conference on Nuclear Engineering, ICONE

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published in (P1433)
Q109039792AN EXPERIMENTAL INVESTIGATION ON POOL ENTRAINMENT UNDER SMALL AIR FLOWRATE
Q119848128APPLICATION RESEARCH OF SMALL MODULAR REACTOR TECHNOLOGY IN FUTURE INTEGRATED ENERGY SYSTEM
Q114967599CODE_ASTER – AN EDF OPEN-SOURCE SOFTWARE TO SOLVE ADVANCED STRUCTURAL PROBLEMS
Q119848125CURRENT ACHIEVEMENTS AND FUTURE TRENDS IN NUCLEAR-POWER INDUSTRY OF THE WORLD
Q109039794EXPERIMENTAL STUDY ON DROPLET-ENTRAINMENT PHENOMENA AT THE INTERFACE OF HIGH-SPEED GAS JET INTO A LIQUID POOL
Q119848186ICONE11-36089 BASIC CONCEPT OF A NEAR FUTURE BWR
Q119848192ICONE11-36180 CURRENT PRODUCTS AND FUTURE PLAN OF REGULATORY RESEARCH FOR RISK-INFORMED REGULATION IN KOREA
Q119848183ICONE11-36222 THE FUTURE OF NUCLEAR : SCWR GENERATION IV HIGH PERFORMANCE CHANNELS
Q119848180ICONE11-36463 HIGH-INERTIA HERMETICALLY SEALED MAIN COOLANT PUMP FOR NEXT GENERATION PASSIVE NUCLEAR POWER PLANTS
Q119848175ICONE11-36508 DEVELOPMENT OF INTERNAL CRD FOR NEXT GENERATION BWR
Q119848171ICONE11-36516 EUROPEAN UTILITY REQUIREMENTS : ACTIONS IN PROGRESS AND NEXT STEPS
Q119848169ICONE11-36520 THE FUTURE OF NUCLEAR ENGINEERING
Q119848167ICONE11-36604 Study on Rewetting of Vertical Narrow Annular Flow Passages By Counter-Current Flow : Examination of Accuracy of Surface Temperature and Heat Flux Derivation
Q122905741ICONE15-10196 LOCAL MEASUREMENTS IN TWO-PHASE FLOW USING A DOUBLE-SENSOR CONDUCTIVITY PROBES AND LASER DOPPLER ANEMOMETRY IN A VERTICAL PIPE
Q120908583ICONE15-10338 FLOW REGIME IDENTIFICATION AND ANALYSIS IN ADIABATIC UPWARD TWO-PHASE FLOW IN AN ANNULUS GEOMETRY
Q118175629ICONE15-10396 Influence of different foundation depths on the seismic response of a next generation nuclear reactor
Q119848161ICONE15-10556 PARADIGMS OF STRUCTURAL SAFETY OF AGED PLANTS : LESSONS LEARNED FROM RUSSIAN ACTIVITIES
Q119848157ICONE15-10618 TWO TYPES OF A PASSIVE SAFETY CONTAINMENT FOR A NEAR FUTURE BWR WITH ACTIVE AND PASSIVE SAFETY SYSTEMS
Q119848154ICONE15-10683 NEW DESIGN PROCEDURE DEVELOPMENT OF FUTURE REACTOR CRITICAL POWER ESTIMATION : (1) PRACTICAL DESIGN-BY-ANALYSIS METHOD FOR BWR CRITICAL POWER DESIGN CORRELATION
Q119848148ICONE15-10741 NEW DESIGN PROCEDURE DEVELOPMENT OF FUTURE REACTOR CRITICAL POWER ESTIMATION : (2) SUB-CHANNEL ANALYSIS FOR SCALE EFFECT ON CRITICAL POWER
Q113239694ICONE19-43265 PUBLIC OFFERING SYSTEM OF RESEARCH AND DEVELOPMENT IDEAS IN JAPC
Q108466885ICONE19-43358 COMPLIANCE WITH APPLICABLE NATIONAL ENVIRONMENTAL POLICY REQUIREMENTS FOR LICENSING A NEW NUCLEAR POWER PLANT WORLD-WIDE
Q110512203ICONE19-43517 Quantification of Severe Accident Source Terms of BWR 4 Reactor with Mark Ι Containment using MAAP 5.00 Code
Q114007592ICONE19-43539 Evaluation of Performance of an Improved Segmented Gamma Scanning Method for the Activity Determination of Radioactive Waste Drums
Q110512204ICONE19-43775 LARGE-EDDY SIMULATION OF CONVECTIVE BOUNDARY LAYER GENERATED BY HIGHLY HEATED SOURCE WITH OPEN SOURCE CODE, OPENFOAM
Q119848145ICONE19-43903 STATUS OF THE HORONOBE UNDERGROUND RESEARCH LABORATORY PROJECT, HOKKAIDO, JAPAN, AND FUTURE PLAN
Q118185649ICONE23-1001 THE COMPONENT OPERATIONAL EXPERIENCE DEGRADATION AND AGEING PROGRAM (CODAP) : REVIEW AND LESSONS LEARNED (2011-2014)
Q114598426ICONE23-1215 APPLICATION OF WIELANDT METHOD IN CONTINUOUS-ENERGY NUCLEAR DATA SENSITIVITY ANALYSIS WITH RMC CODE
Q119848140ICONE23-1333 The Effect of Spacer Grid's Elements on the Rewetting Velocity
Q114057763ICONE23-1475 APPLICATION OF THE ODD-EVEN METHOD FOR TIME-DEPENDENT 3D NEUTRON DIFFUSION CALCULATION
Q114608627ICONE23-1570 THE FLOW AND HEAT TRANSFER CHARACTERISTICS OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITIONS
Q114598425ICONE23-1655 DEVELOPMENT OF HYDROGEN BEHAVIOR SIMULATION CODE SYSTEM : OUTLINE OF CODE SYSTEM AND VALIDATION USING EXISTING DATA
Q119848138ICONE23-1670 DEVELOPMENT OF THE PREDICTION TECHNOLOGY OF CABLE DISCONNECTION OF IN-CORE NEUTRON DETECTOR FOR THE FUTURE HIGH-TEMPERATURE GAS COOLED REACTORS
Q119848134ICONE23-1686 UPDATE ON THE FUKUSHIMA ACCIDENT AND TECHNICAL LESSONS LEARNED FOR WATER COOLED REACTOR TECHNOLOGY DEVELOPMENT
Q114608625ICONE23-1838 OPERATIONAL CHARACTERISTICS OF PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITION
Q119848132ICONE23-2009 OUTLINES OF JAEA'S INSTRUCTOR TRAINING PROGRAM AND FUTURE PROSPECTS
Q110828254ICONE23-2064 GROUNDWATER FLOW MODELING FOCUSED ON THE FUKUSHIMA DAIICHI NUCLEAR POWER PLANT SITE
Q119848123NID “NUCLEAR INNOVATIVE DESIGN” PROJECT – PROMOTING INNOVATION ON RUPTURE FOR NPP’S FUTURE
Q109039797NUMERICAL INVESTIGATION OF SUBMERGED JET FLOW ENTRAINMENT BEHAVIOR ADJACENT TO NOZZLE
Q124839004PARAMETER OPTIMIZATION OF HTR-10 ONLINE BURNUP MEASUREMENT DETECTOR SYSTEM USING META-HEURISTIC ALGORITHMS
Q124130257PROPOSAL FOR OPEN-SOURCE GNDS-JSON FORMAT WITH REDUCED NUCLEAR DATA STRUCTURAL COMPLEXITY
Q124884313Summary of Lagrangrian Transport Models of Radionuclides in the Marine Environment
Q126525075TRANSIENT RESPONSE CHARACTERISTICS IN MULTI-LOOP NATURAL CIRCULATION SYSTEM USING FREQUENCY RESPONSE TESTING METHOD

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