Organizations

AE Engineering

Bolted flanged connection on a basis of shape memory effect and inverse flexion flange design

AEOI, Nuclear Research Centre

SIMULATION OF HORIZONTAL STEAM GENERATORS USING NEURAL NETWORKS

Armenian NPP

OPERATING EXPERIENCE OF STEAM GENERATORS AT ARMENIAN NPP

CJSC “Diaprom”

MONITORING OF HEAT-MECHANIC STATES OF PGV-1000M

Department of Electrical and Computer Engineering, Tehran University

SIMULATION OF HORIZONTAL STEAM GENERATORS USING NEURAL NETWORKS

Department of Mechanical Engineering, Sharif University of Technology

SIMULATION OF HORIZONTAL STEAM GENERATORS USING NEURAL NETWORKS

ENIMTS «Simulating systems»

MODEL FOR EXAMINATION OF THERMAL HYDRAULICS OF HORIZONTAL STEAM GENERATORS, INITIAL GOALS AND OBJECTIVES OF WORK

VERIFICATION OF TRAC CODE USING HYDRODYNAMICAL MODEL OF PGV-1500 TUBE BUNDLE

Energy Institute JSC

DEVELOPMENT OF A NEW METHOD FOR MBF ION EXCHANGE RESINS SEPARATOIN AND OPTIMIZATION OF VVER 1000 CONDENSATE POLLISHING SYSTEM OPERATION

FSUE Alexandrov NITI

EFFICIENCY ANALYSIS OF SOLUTION FORMULAS AND TECHNOLOGIES FOR CLEANING STEAM GENERATORS OF SG-440 AND SGV-1000M TYPES

FSUE CRISM «Prometey»

THE DYNAMICS OF NUCLEATION AND PROPAGATION OF DAMAGES IN HEAT-EXCHANGING PIPES (HEP) OF STEAM-GENERATORS (SG) PGV-1000 V DURING NORMAL OPERATING CONDITIONS

THE BASIC MECHANISMS OF STEAM GENERATOR PGV-1000 HEAT EXCHANGING PIPES DAMAGE AT VARIOUS OPERATION CONDITIONS

FSUE Concern «Rosenergoatom»

MONITORING OF HEAT-MECHANIC STATES OF PGV-1000M

EXPERIENCE OF APPLICATION ON NPP РД ЭО-0552-2004 "METHODICAL RECOMMENDATIONS FOR APPLICATION OF SYSTEM METHODOLOGY FOR MAINTENANCE OF SG TUBES INTEGRITY OF THE NPP WITH WWER"

DEVELOPMENT OF THE ATLAS OF DEFECTS OF STEAM GENERATORS HEAT EXCHANGING TUBES OF THE NPPs WITH WWER

EXAMINATION OF SOFTWARE FOR TUBE DEFECT DETECTION AND PARAMETERISATION USING WWER STEAM GENERATOR EDDY CURRENT TESTING DATA

FSUE LI «VNIPIET»

WORKING OUT OF OPERATIONAL CONTROL METHOD OF STEAM GENERATOR ELEMENTS CORROSION

COMPARATIVE ANALYSIS OF NORMALIZED INDICES OF BOILING CIRCUITS COOLANT OF NPP WITH DIFFERENT REACTOR TYPE AND CONSTRUCTIONS

FSUE NIAEP

SOME ASPECTS OF ALGORITHMS AND SOFTWARE DEVELOPMENT FOR WWER NPP'S PRIMARY AND SECONDARY CIRCUITS WC CONTROL AND MONITORING SYSTEM (CMS) UPPER LEVEL REGARDING DIAGNOSTIC FUNCTION INITIATING

FSUE «Atomenergoremont»

STEAM GENERATOR HEAT EXCHANGE PIPE EDDY-CURRENT INSPECTION EXPERIENCE

FSUE «GIDROPRESS»

JUSTIFICATION OF THE REQUIREMENTS FOR EDDY CURRENT CONTROL OF HEAT EXCHANGING TUBES OF HORIZONTAL STEAM GENERATORS

ELABORATION OF APPROACH FOR EVALUATION OF OPTIMAL PERIODICITY OF EDDY CURRENT CONTROL OF HEAT EXCHANGING TUBES OF HORIZONTAL STEAM GENERATORS

CALCULATION OF HYDRODYNAMICS OF DESIGN OF PGV-1500 SG PRIMARY-SIDE FLOW PART USING CFD-CODES

INVESTIGATION OF STRESS CONCENTRATION NEAR THE PERFORATION HOLES OF STEAM GENERATOR ELEMENTS IN THREE-DIMENSIONAL STATEMENT

MODEL FOR EXAMINATION OF THERMAL HYDRAULICS OF HORIZONTAL STEAM GENERATORS, INITIAL GOALS AND OBJECTIVES OF WORK

ELABORATION OF ISOLATION DEVICE FOR STEAM GENERATOR PGV-1000

SYSTEM OF HYDRODYNAMICAL WASHING OF THE STEAM GENERATOR TUBE BUNDLE

A STUDY TO SUBSTANTIATE THE MATERIAL SCIENCE ASPECTS OF PHRS DESIGN FOR TROPICAL CLIMATE CONDITIONS

FEATURES OF BEHAVIOUR OF LOW-ALLOYED STEELS IN HIGH-TEMPERATURE WATER UNDER STRESS CORROSION CONDITIONS; THE BASIC CONCEPT OF DELAYED STRAIN CORROSION CRACKING (ЗДКР) AS APPLIED TO OPERATION CONDITIONS OF STEAM GENERATORS OF NPP WITH WWER

FIELD OBSERVATIONS OF THE THERMAL STRESS CONDITION OF THE FEEDWATER NOZZLE OF STEAM GENERATOR PGV-1000

THE CALCULATIVE ANALYSIS OF FACTORS OF ADDITIONAL FORCE INFLUENCE IN A NOZZLE OF SG COLLECTOR TO SG BRANCH WELDING DURING A REPAIR AND OPERATION

WORKING OUT OF OPERATIONAL CONTROL METHOD OF STEAM GENERATOR ELEMENTS CORROSION

SIMULATION OF TRANSIENT THERMAL-HYDRAULIC PROCESSES IN STEAM-GENERATORS OF VVER-1000 REACTOR PLANTS, USING MODIFIED VERSION OF THE KORSAR COMPUTER CODE

SOME RESULTS OF STEAM GENERATOR COMPLEX THERMOCHEMICAL TRIALS WITH USING OF EXPERIMENTAL PROBE SYSTEM IN THE TIME OF OPERATION IN AMMONIA-HIDRAZINE AND MORPHOLINE WATER CHEMISTRY REGIMES. ROSTOV NPP UNIT 1

VERIFICATION OF TRAC CODE USING HYDRODYNAMICAL MODEL OF PGV-1500 TUBE BUNDLE

ANALYSIS OF THE THERMALHYDRAULIC PROCESSES IN HORIZONTAL STEAM GENERATOR WITH STEG CODE

ASSESSMENT OF PROBABILITY OF PGV-1000 COLLECTOR COVER LIFT-OFF USING THE PROBABILISTIC METHODS OF FRACTURE MECHANICS

DEVELOPMENT OF THE ATLAS OF DEFECTS OF STEAM GENERATORS HEAT EXCHANGING TUBES OF THE NPPs WITH WWER

OPERABILITY OF HEAT EXCHANGING TUBES AND MANAGEMENT OF SEVICE LIVE OF NPP WITH WWER

OPTIMIZATION OF COLLECTOR –TO-STEAM GENERATOR VESSEL WELDING UNIT

RESEACH OF UPGRADED SEPARATION SYSTEM PGV-1500

STEAM GENERATOR DEACTIVATION FACILITY AT RP WITH WWER-1000

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

INTEGRITY OF HEAT EXCHANGING TUBES OF VERTICAL AND HORISONTAL STEAM GENERATORS (COMPARATIVE ANALYSIS)

ISSUES OF SERVICE LIFE PROPLONGATION OF STEAM GENERATORS AT NPP WITH WWER-440

PAST AND FUTURE OF HORIZONTAL STEAM GENERATORS

OPTIMIZATION OF PERFORATION OF THE DISTRIBUTION PERFORATED PLATE IN PGV-1500

THE DYNAMICS OF NUCLEATION AND PROPAGATION OF DAMAGES IN HEAT-EXCHANGING PIPES (HEP) OF STEAM-GENERATORS (SG) PGV-1000 V DURING NORMAL OPERATING CONDITIONS

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

THE BASIC MECHANISMS OF STEAM GENERATOR PGV-1000 HEAT EXCHANGING PIPES DAMAGE AT VARIOUS OPERATION CONDITIONS

ANALYSIS OF CAUSES OF METAL DAMAGE IN THE AREA OF WELD No 111 OF PGV-1000M STEAM GENERATORS

ASSESSMENT OF STRESS INTENSITY IN THE WELDED JOINT OF THE COLLECTOR TO THE NOZZLE OF SG PGV-1000 DURING OPERATION AND POST-REPAIR HEAT TREATMENT

FSUE “EREC”

EFFECT OF THE METAL CHEMICAL COMPOSITION ON THE SERVICEABILITY OF THE SG HEAT EXCHANGING TUBES AT THE NPPS WITH VVER

ANALYSIS OF THE THERMALHYDRAULIC PROCESSES IN HORIZONTAL STEAM GENERATOR WITH STEG CODE

COMPARISON OF THE NUMBER OF THE SG HEAT EXCHANGING TUBES PLUGGED AT THE NPPS WITH VVER, PREDICTABLE THROUGH PROBABILISTIC APPROACHES WITH THEIR NUMBER OBSERVED

RESEACH OF UPGRADED SEPARATION SYSTEM PGV-1500

FSUSE «Atomtechenergo», Myticshi

FIELD OBSERVATIONS OF THE THERMAL STRESS CONDITION OF THE FEEDWATER NOZZLE OF STEAM GENERATOR PGV-1000

COMPARATIVE TRIALS OF LEVEL MEASUREMENT SYSTEM FOR STEAMGENERATORS WITH DIFFERENT INTERNALS

FSUSE “Atomtechenergo”, “KalininAtomTechEnergo”

COMPARATIVE TRIALS OF LEVEL MEASUREMENT SYSTEM FOR STEAMGENERATORS WITH DIFFERENT INTERNALS

CHOICE AND OPTIMIZATION OF SG BLOWDOWN MODE AT KALININ NPP

INETEC - Institute for Nuclear Technology

AN APPROACH TO ADDITIONAL PERFORMANCE DEMONSTRATION OF MECHANICAL PLUGGING TECHNOLOGY

JSC Engineering Company ZIOMAR

MANUFACTURING EXPERIENCE OF STEAM GENRATORS FOR NPP WITH VVER-1000 REACTOR

JSC Machine-Building Plant ZIO-Podolsk

MANUFACTURING EXPERIENCE OF STEAM GENRATORS FOR NPP WITH VVER-1000 REACTOR

JSC R&PA “TsNIITMASH”

A STUDY TO SUBSTANTIATE THE MATERIAL SCIENCE ASPECTS OF PHRS DESIGN FOR TROPICAL CLIMATE CONDITIONS

FEATURES OF BEHAVIOUR OF LOW-ALLOYED STEELS IN HIGH-TEMPERATURE WATER UNDER STRESS CORROSION CONDITIONS; THE BASIC CONCEPT OF DELAYED STRAIN CORROSION CRACKING (ЗДКР) AS APPLIED TO OPERATION CONDITIONS OF STEAM GENERATORS OF NPP WITH WWER

JSC «Scientific and technical centre», Ukraine

EFFICIENCY OF THE SAFETY ENHANCEMENT MEASURES PROVIDED FOR STEAM GENERATORS PGV-1000M AT UKRAINE NPPS

JSC “VNIIAES”

THE CALCULATIVE ANALYSIS OF FACTORS OF ADDITIONAL FORCE INFLUENCE IN A NOZZLE OF SG COLLECTOR TO SG BRANCH WELDING DURING A REPAIR AND OPERATION

MONITORING OF HEAT-MECHANIC STATES OF PGV-1000M

ACCOUNT RESEARCH OF INFLUENCE OF HYDROTESTS AND NONDESTRUCTIVE EVALUATION ON RELIABILITY OF A STEAM GENERATOR TUBING

EXPERIENCE OF APPLICATION ON NPP РД ЭО-0552-2004 "METHODICAL RECOMMENDATIONS FOR APPLICATION OF SYSTEM METHODOLOGY FOR MAINTENANCE OF SG TUBES INTEGRITY OF THE NPP WITH WWER"

DEVELOPMENT OF THE ATLAS OF DEFECTS OF STEAM GENERATORS HEAT EXCHANGING TUBES OF THE NPPs WITH WWER

KCN BRAS

ACCOUNT RESEARCH OF INFLUENCE OF HYDROTESTS AND NONDESTRUCTIVE EVALUATION ON RELIABILITY OF A STEAM GENERATOR TUBING

Kalinin NPP

COMPARATIVE TRIALS OF LEVEL MEASUREMENT SYSTEM FOR STEAMGENERATORS WITH DIFFERENT INTERNALS

CHOICE AND OPTIMIZATION OF SG BLOWDOWN MODE AT KALININ NPP

SOME ASPECTS OF ALGORITHMS AND SOFTWARE DEVELOPMENT FOR WWER NPP'S PRIMARY AND SECONDARY CIRCUITS WC CONTROL AND MONITORING SYSTEM (CMS) UPPER LEVEL REGARDING DIAGNOSTIC FUNCTION INITIATING

Kola NPP

ANALYSIS AND EVALUATION OF KOLA NPP STEAM GENERATOR HEAT-EXCHANGE TUBES EDDY–CURRENT TEST RESULTS

EXAMINATION OF SOFTWARE FOR TUBE DEFECT DETECTION AND PARAMETERISATION USING WWER STEAM GENERATOR EDDY CURRENT TESTING DATA

MEI, Moscow

EFFECTIVE EDDY CURRENT SIGNAL PROCESSING ALGORITHMS FOR TESTING WWER STEAM GENERATOR HEAT EXCHANGER TUBES

DEVELOPMENT OF NEURAL NETWORK DEFECT CLASSIFIER FOR MULTIFREQUENCY EDDY CURRENT TESTING OF HEAT EXCHANGER TUBES

EXAMINATION OF SOFTWARE FOR TUBE DEFECT DETECTION AND PARAMETERISATION USING WWER STEAM GENERATOR EDDY CURRENT TESTING DATA

NICE «Centrenergo»

SOME RESULTS OF STEAM GENERATOR COMPLEX THERMOCHEMICAL TRIALS WITH USING OF EXPERIMENTAL PROBE SYSTEM IN THE TIME OF OPERATION IN AMMONIA-HIDRAZINE AND MORPHOLINE WATER CHEMISTRY REGIMES. ROSTOV NPP UNIT 1

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

NPP Operation Support Institute, Kiev

TYPICAL ASSESSMENT PROGRAM OF TECHNICAL CONDITION AND RESOURCE REASSIGNMENT OF UKRAINIAN NPPS’ STEAM GENERATORS

NRI Rez, Czech Rep.

ELECTROCHEMICAL EVALUATION SYSTEM. MODULAR SYSTEM FOR LONG-TERM ON-LINE MONITORING OF CORROSION PROCESSES IN STRUCTURAL CREVICES OF STEAM GENERATOR SECONDARY CIRCUIT

PROBABILITY OF WWER STEAM GENERATOR TUBES AND COLLECTOR LIGAMENT CORROSION CRACK DETECTION.

Maintenance capability of NRI Řež for WWER steam generators.

National Nuclear Energy Generating Co. «Energoatom»

TYPICAL ASSESSMENT PROGRAM OF TECHNICAL CONDITION AND RESOURCE REASSIGNMENT OF UKRAINIAN NPPS’ STEAM GENERATORS

EXPERIENCE IN REALIZATION OF THE PROGRAM RELATED TO RELIABILITY INCREASING OF SG IN NPP OF UKRAINE

Novovoronezh NPP

SPECIFIC FEATURES OF WATER CHEMISTRY FOR STEAM GENERATORS PGV-440 AT NOVOVORONEZH UNITS 3-4

DECONTAMINATION OF STEAM GENERATORS PGV-440

EMERGENCY SHUTDOWN OF 3SG-4 AT NOVOVORONEZH NUCLEAR POWER PLANT DUE TO TUBE CRACK FORMATION, TRANSIENT DYNAMICS AND METHOD OF BRINGING SG AND REACTOR PLANT TO SAFE CONDITION

Paks NPP, Hungary

AGING MANAGEMENT AND MATERIAL DEGRADATION MONITORING OF SG AT PAKS NPP

RRC «Kurchatov institute», Moscow

ACCOUNT RESEARCH OF INFLUENCE OF HYDROTESTS AND NONDESTRUCTIVE EVALUATION ON RELIABILITY OF A STEAM GENERATOR TUBING

EXPERIENCE OF APPLICATION ON NPP РД ЭО-0552-2004 "METHODICAL RECOMMENDATIONS FOR APPLICATION OF SYSTEM METHODOLOGY FOR MAINTENANCE OF SG TUBES INTEGRITY OF THE NPP WITH WWER"

Reliability of machines and constructions, Kiev

ASSESSMENT OF STRESS INTENSITY IN THE WELDED JOINT OF THE COLLECTOR TO THE NOZZLE OF SG PGV-1000 DURING OPERATION AND POST-REPAIR HEAT TREATMENT

Rostechnadzor Russia, Novovoronezh

THE CALCULATIVE ANALYSIS OF FACTORS OF ADDITIONAL FORCE INFLUENCE IN A NOZZLE OF SG COLLECTOR TO SG BRANCH WELDING DURING A REPAIR AND OPERATION

SPC NDT “ECHO+”

EQUIPMENT AND PROCEDURES OF AUTOMATED ULTRASONIC TESTING OF THE WELDING JOINT OF THE HEAT-CARRYING COLLECTOR WITH THE SOCKET OF THE VVER 440 AND VVER 1000 STEAM GENERATORS

SRC RF - IPPE

MODEL FOR EXAMINATION OF THERMAL HYDRAULICS OF HORIZONTAL STEAM GENERATORS, INITIAL GOALS AND OBJECTIVES OF WORK

VERIFICATION OF TRAC CODE USING HYDRODYNAMICAL MODEL OF PGV-1500 TUBE BUNDLE

RESEACH OF UPGRADED SEPARATION SYSTEM PGV-1500

OPTIMIZATION OF PERFORATION OF THE DISTRIBUTION PERFORATED PLATE IN PGV-1500

THE LOCAL PROBLEMS OF DEPOSITION LAYER GROWTH ON THE HORIZONTAL STEAM GENERATOR TUBES

Saint-Petersburg State Polytechnical University

HORISONTAL STEAM GENERATOR UNDER NATURAL PRIMARY COOLANT CIRCULATION CONDITIONS

State scientific and technical centre on nuclear and radiation safety, Kiev

TYPICAL ASSESSMENT PROGRAM OF TECHNICAL CONDITION AND RESOURCE REASSIGNMENT OF UKRAINIAN NPPS’ STEAM GENERATORS

Strength Problem Institute named after G.S.Pisarenko of NAS of the Ukraine

ASSESSMENT OF STRESS INTENSITY IN THE WELDED JOINT OF THE COLLECTOR TO THE NOZZLE OF SG PGV-1000 DURING OPERATION AND POST-REPAIR HEAT TREATMENT

VEIKI, Hungary

AGING MANAGEMENT AND MATERIAL DEGRADATION MONITORING OF SG AT PAKS NPP

VUJE, a.s. Trnava, Slovak Republic

EDDY CURRENT INSPECTION OF WWER STEAM GENERATOR TUBES - SENSITIVITY OF BOBBIN PROBE TECHNIQUE.

Analysis of long - term operation influence on the degradation of VVER-440 steam generator piping

Volgodonsk NPP

SOME RESULTS OF STEAM GENERATOR COMPLEX THERMOCHEMICAL TRIALS WITH USING OF EXPERIMENTAL PROBE SYSTEM IN THE TIME OF OPERATION IN AMMONIA-HIDRAZINE AND MORPHOLINE WATER CHEMISTRY REGIMES. ROSTOV NPP UNIT 1

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

RESULTS OF CHEMICAL CLEANINGS OF STEAM GENERATORS VOLGODONSK NPP UNIT 1 BEFORE THE SHEDULED MAINTENANCE -2005, 2006

VÍTKOVICE HEAVY MACHINERY

THE SIMULTANEOUS EFFECT OF AGEING AND WATER ENVIRONMENT ON SUBCRITICAL CRACK GROWTH AND FRACTURE BEHAVIOUR OF 10GN2MFA LOW ALLOY STEEL

VÍTKOVICE-Research Development, Ltd.,

THE SIMULTANEOUS EFFECT OF AGEING AND WATER ENVIRONMENT ON SUBCRITICAL CRACK GROWTH AND FRACTURE BEHAVIOUR OF 10GN2MFA LOW ALLOY STEEL

ČEZ, a.s., NPP Temelin

STEAM GENERATOR CHEMISTRY IN TEMELIN NPP OPERATIONAL EXPERIENCE

русский
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