THE ELEVENTH INTERNATIONAL CONFERENCE ON MATERIAL ISSUES IN DESIGN, MANUFACTURING AND OPERATION OF NUCLEAR POWER PLANTS EQUIPMENT PROGRAMME - PDF

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Central Research Institute of Structural Materials «Prometey in cooperation with the International Atomic Energy Agency and Joint Research Center of European Commission THE ELEVENTH INTERNATIONAL CONFERENCE
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Central Research Institute of Structural Materials «Prometey in cooperation with the International Atomic Energy Agency and Joint Research Center of European Commission THE ELEVENTH INTERNATIONAL CONFERENCE ON MATERIAL ISSUES IN DESIGN, MANUFACTURING AND OPERATION OF NUCLEAR POWER PLANTS EQUIPMENT PROGRAMME CRISM Prometey Saint-Petersburg June 2010 ORGANIZERS OF THE CONFERENCE CRISM Prometey Concern ROSENERGIATOM Science and High School Department of St. Petersburg Administration St. Petersburg Society of Science and Technology GENERAL SCHEDULE June, 14 (Monday) June, 15 (Tuesday) June, 16 (Wednesday) June, 17 (Thursday) June, 18 (Friday) Arrival of participants. Registration of participants. Excursion Program. Registration of participants. Opening of the Conference. Plenary Session 1. Sections 1-3 Meetings. Welcome party. Plenary Session 2. Sections 1-3 Meetings. Plenary Session 3. Section 1-3 meetings. Plenary Session 4 Closing of the Conference. Progress Meeting. Excursion Program. Departure of participants. Whole day From 12 to 18 hrs From 15 to 20 hrs From 9 to 10 hrs 10 hrs From 10 to 12 hrs From 13 to 18 hrs From 19 to 21 hrs From 9 to 11 hrs From 11 to 18 hrs From 9 to 11 hrs From 11 to 14 hrs From 15 to 17 hrs From 17 to 18 hrs From 10 to 17 hrs From 10 to 13 hrs Whole day Conference venue Kochubey Palace (town Pushkin, Radishcheva str.,4) Plenary sessions and meetings of session 1 Hall No.1 Meetings of session 2 Room No. 2 Meetings of session 3 Room No. 3 p. 2 June 15, 2010 (Tuesday). 9:00 10:00. Registration of participants PLENARY SESSION No.1. June 15, (Tuesday), Hall No 1. Chairmen: I.Gorynin and G.Karzov (Russia) 10:00. Opening of the Conference. Opening Address of the CRISM «Prometey President Academician I.V.Gorynin. Main Topics of the Eleventh International Conference on Nuclear Power Engineering. 10:15. General Director of CRISM «Prometey А.S.Oryshchenko. Experience of Structural Material Development and Application for Nuclear Power Installation Equipments Deputy of the General Director of CRISM Prometey G.P.Karzov. Material Science and Methodical Issues of Lifetime Management of RPV and Internals of WWER :15. Deputy of the General Director of CRISM Prometey V.P.Leonov. Usage of Titanium Alloys in NPP Equipment (Authors: I.V.Gorynin, А.S.Оryshchenko, V.P.Leonov, V.I.Мikhailov, I.А.Schastlivaya). 11:45. Head of Department of RRC Kurchatov Institute B.А. Gurovich. Annealing Effect of Irradiatied RPV Materials for Prolongation of WWER-1000 Lifetime up to 60 Years (Authors: Ya.I.Shtrombakh, B.А.Gurovich, Е.А.Кuleshova, D.Yu.Еrak, S.V.Fedotova, D.А.Zhurko, О.О.Zabusov, Yu.А.Nikolaev). 12:15 12:45. Coffee break Session 1. Material Mechanical Properties, Strength and Fracture Criteria and Limit Conditions for Structure Components. Meeting 1-1. June 15 (Tuesday). 12:45-14:00. Hall No 1. Chairmen: B. Margolin (Russia) and F. Gillemot (Hungary). 1. Local Criterion of Brittle Fracture and Embrittlement of Reactor Pressure Vessel Steels. B.Z.Margolin, V.A.Shvetsova, A.G.Gulenko, E.V.Nesterova (FSUE CRISM Prometey, St. Petersburg, 2. Post Modern Investigations of Greifswald WWER-440 Reactor Pressure Vessels. H.-W.Viehrig, M.Houska, U.Rindelhardt (Institute p. 3 of Safety Research, Forschungszentrum Rosseendorf, Dresden, Germany). 3. Study of RPV Cladding Ageing. F.Gillemot (MTA KFKI AEKI, Budapest, Hungary). 4. New Approach to Choice of Potential Parameters for Моlеcular- Dynamic Modeling Properties of Uranium Dioxide Properties. Yu.S.Nagornov, R.Yu.Makhmud-AKhunov, B.M.Kostishko, V.N.Golovanov (Uliyanovsky State University, Uliyanovsk, 14:00-15:00. Lunch. Meeting 1-2. June 15 (Tuesday). 15:00-18:00. Hall No 1 Chairmen: V.Shvetsova (Russia) and U.Rindelhardt (Germany). 1. Analysis of Materials Embrittlement for WWER-1000 Reactor Pressure Vessels during Operation. B.Z.Margolin, V.A.Nikolaev, E.V.Yurchenko (FSUE CRISM Prometey, St. Petersburg, Russia), Yu.A.Nikolaev, A.V.Nikolaeva, D.Yu.Erak (RRC Kurchatov Institute, Moscow, 2. Investigation of Mechanical Properties and Fine Structure of the Irradiated, Annealed and Re-Irradiated WWER-440 RPV Steels. S.V.Rogozhkin, A.A.Aleev, A.G.Zaluzhniy, A.A.Nikitin (SSC RF Institute for Theoretical and Experimental Physics, Moscow, Russia), A.A.Chernobaeva, D.Yu.Erak, O.O.Zabusov, Ya.I.Shtrombakh (RRC Kurchatov Institute, Moscow, 3. Investigation of Nano-Scaled Features in Un-Irradiated and Irradiated ODS EUROFER by Tomography Atom Probe. S.V.Rogozhkin, A.A.Aleev, A.G.Zaluzhniy, A.A.Nikitin, N.A.Iskandarov (SSC RF Institute for Theoretical and Experimental Physics, Moscow, Russia), P.Vladimirov, R.Lindau, A.Moslang (Karlsruhe Institute of Technology, Institute for Material Research-I, Karlsruhe, Germany). 4. The Doze Dependences for Prediction Irradiation Embrittlement of Russian Materials for WWER-440. G.P.Karzov, B.Z.Margolin, V.A.Nikolaev, A.M.Morozov, E.V.Yurchenko, D.A.Chistyakov, N.E.Pirogova (FSUE CRISM Prometey, St. Petersburg, 16:20-16:40. Coffee break 5. Fracture Mechanics Based Applicability Substantiation of Materials for Welded Non-Heat-Treated Structures Made of High Strength Steels. A.V.Ilyin, O.P.Vinogradov, V.Yu.Filin (FSUE CRISM Prometey, St. Petersburg, p. 4 6. Calculation of Durability of Homogeneous and Dissimilar Welded Joints with a Soft Layer. T.V.Prokhorova, A.A.Lanin (Central Research Institute of Steam Boilers and Turbines, St. Petersburg, 7. Calculative Determination of Threshold Displacement Energy near Extended Inter-Phase Boundary between Zr and Nb: the Molecular Dynamics Simulation. M.Yu.Tikhonchev (Ulyanovsk State University, Ulyanovsk, 8. Improvement in the Efficiency of Irradiated Materials Using by Means of the Reconstruction Technique of Mini-Charpy Samples from Ferrite-Martensite Steel. S.A.Frolov, E.M.Tabakin (JSC SSC RIAR, Dimitrovgrad, Session 2. Operation Experience and Life Time Management. Meeting 2-1. June 15 (Tuesday). 12:45-14:00. Hall No 2. Chairmen: V.Piminov (Russia) and P.Kauppinen (Finland). 1. Control of the Service Life and NPP System over Mathematical Modeling Processes of Degradation of Structural Materials under Operation Conditions. F.M.Mitenkov, D.L.Zverev, V.B.Kaidalov, Yu.G.Korotkikh, V.A.Panov, V.A.Pakhomov (JSC Afrikantov OKBM, Nizhnji Novgorod, 2. Features of Calculation of Stress Intensity State Kinetics of WWER RPV with Defects at Thermal Shock. V.V.Kharchenko, A.Yu.Chirkov, S.V.Kobelsky, V.I.Kravchenko, A.A.Khodakovsky, S.N.Baniko (Strength Problems Institute, Kyev, Ukraine) 3. WWER-1000 RPV Lifetime Extension from Brittle Failure Resistance Point of View. I.F.Akbashev, V.A.Piminov (JSC OKB Gidropress, Podolsk, Russia), B.Z.Margolin (FSUE CRISM Prometey, St. Petersburg, 4. Application of Risk-Informed Approach to the In-Service Inspection Programme of Unit 1 of Loviisa NPP. P.Kauppinen (Technical Research Centre of Finland, Helsinki, Finland), O.Hietanen, K.Jankala, V.Nikula, R.Paussu (Fortum Nuclear Services LTD, Helsinki, Finland) 14:00-15:00. Lunch. Meeting 2-2. June 15 (Tuesday). 15:00-18:00. Hall No 2. Chairmen: A.Lanin (Russia) and M.Kytka (Czech Republic) p. 5 1. Methodical Maintenance of Substantiation of Lifetime Extension for WWER-1000 RPV. V.A.Varovin, B.Z.Margolin, V.I.Kostylev, V.N.Fomenko, V.A.Shvetsova (FSUE CRISM Prometey, St. Petersburg, 2. Extended Surveillance Specimen Programme for WWER-440 Life Extension. M.Brumovsky, M.Kytka (Nuclear Research Institute Rez plc, Rez, Czech Republic). 3. Pre-Requisites to PWRs Surveillance Program Modernization. E.A.Krasikov, P.A.Platonov, S.V.Kotlov (RRC Kurchatov Institute , Moscow, Russia) 4. Assessment of Acceptable Flaw Size in Core Shroud Cover for a BWR Reactor. A.Shipsha, J.Gunnars, J.Mullins (Inspect Technology AB, Stockholm, Sweden), W.Zang (OKG/EON Group) 16:20-16:40. Coffee break 5. Current status of in-service inspection updating at Paks NPP. J.Pinczés, D.Szabó, S.Rátkai (Paks NPP, Paks, Hungary), P.Trampus (Trampus Consulting & Engineering, Bicske, Hungary) 6. Estimation of State for Base Metal and Welded Joints of Steam Generator PGV-440 of the First Generation after 37 Years Operation of Novo-Voronezh NPP. V.V.Jbannikov, A.N.Prytkov, M.P.Slivkin (Novo-Voronezh NPP, Novo-Voronezh, Russia) 7. Up-to-date Elementary Analysis Methods for Post-Irradiation Examination of Structural Materials. G.V.Shishalova, A.V.Povstyanko, G.P.Kobylyansky (JSC SSC RIAR, Dimitrovgrad, Russia) Session 3. Modern Tendencies in Material Creation and Advanced Technologies for NPP Components. Meeting 3-1. June 15 (Tuesday). 12:45-14:00. Hall No 3. Chairmen: G. Karzov (Russia) and P.Babics (Hungary) 1. New Principles of Increasing Operation Characteristics for Heat- Resistant Steels Used for Nuclear Power Engineering. G.P.Karzov, I.V.Teplukhina (FSUE CRISM Prometey, St. Petersburg, 2. Computer Modeling of Heat-Exchange Character and Microstructure Forming in a Butt Zone of Large-Sized Forgings Made of Cr-Mo-V Steel for Nuclear Power Plant Vessels. V.M.Golod (St. Petersburg State Polytechnic University, St. p. 6 Petersburg, Russia), G.P.Karzov, I.V.Teplukhina (FSUE CRISM Prometey, St. Petersburg, 3. Elevation of Cold-Resistance of the Heat Affected Zone from the Low-Carbon Si-Mn Steels. M.I.Olenin, N.G.Bykovsky, V.I.Gorynin, N.V.Lebedeva (FSUE CRISM Prometey, St. Petersburg, 4. Influence of 15Cr2NiMoVA Steel Deoxidation Method in the Process of Out-Furnace Steel Treatment on Change in Composition and Morphology of Non-Metallic Inclusions. L.T.Afanasyeva, T.I.Titova, S.A.Chernyahovsky, I.B.Zenkov (Research Centre TC OMZ-Izhora LTD, St. Petersburg, Russia), Yu.M.Batov, S.J.Afanasyev ( OMZ-Spezstal LTD, St. Petersburg, 14:00 15:00. Lunch Meeting 3-2. June 15 (Tuesday). 15:00-18:00. Hall No 3. Chairmen: T.Titova (Russia) and L.Rissanen (Finland). 1. Experience Gained from Application of De-Hydrogenation Treatment when Manufacturing Thick-Wall Weld Joints of Low- Alloy Cr-Mo and Cr-Mo-V Steel Grades. A.S.Borovskoy, I.F.Semernina, S.A.Bocharov. (Research Centre TC OMZ-Izhora LTD, St. Petersburg, 2. Investigation of Hot Plasticity for High Chromium Material Steels. B.M.Shljakman, D.V.Ratushev, C.E.Shklyaev (Research Centre TC OMZ-Izhora LTD, St. Petersburg, 3. Technological and Operational Strength of Perlite Cladding on 9-12% Cr Steel. A.A.Lanin, S.A.Ilyin, Yu.G.Diyakov, T.V.Prokhorova (Central Research Institute of Steam Boilers and Turbines, St. Petersburg, 4. New Steels with Yield Strength of 450 MPa at Elevated Temperature for WWER RPV with Service Life 60 Years. A.M.Morozov, G.P.Karzov, I.V.Teplukhina (FSUE CRISM Prometey, St. Petersburg, 16:20-16:40. Coffee break 5. Welding Procedure in Solid Phase for Couple Materials Zr-Alloy E- 635 and Austenitic Steel 08Cr18Ni10Ti. I.A. Hazov, L.V. Selezneva (Research-and-Production Centre INTECO Federal state unitary enterprise Red Star , Moscow, Russia), G.V.Dubinin, S.N.Novozhilov, A.N.Semenov (NIKIET, Moscow, Russia), p. 7 M.S.Metalnikov, R.A.Tupikov (JSC OKB Gidropress, Podolsk, 6. Application of Mobile Spectrometer PMI-Master Plus for the Chemical Composition Control for Pressure Tanks of Responsible Function. O.V.Kiselev, L.S.Matveeva, I.S.Shkljaeva, E.G.Nikitina (Research Centre TC OMZ-Izhora Ltd, St. Petersburg, 7. Research of Fracture Toughness Characteristics of Welded High- Strength Titanium Alloys for Hull Construction. A.S.Kudryavtsev, D.A.Panotskiy (FSUE CRISM Prometey, St. Petersburg, 19:00 21:00. Welcome Party. June 16, 2010 (Wednesday). PLENARY SESSION 2. June 16, (Wednesday), Hall No 1. Chairmen: B.Gurovich (Russia) and M.Brumovsky (Czech Republic). 9:00. Head of Department of IMASH of RAS N.А.Makhutov. Substantiation of Material Selection on Parameters of Strength, Durability and Safety of Structures (Authors: N.A. Makhutov, M.M. Gadenin). 9:30. Project Manager of Nuclear Research Institute (Rez plc) М.Brumovsky. Transformation of the VERLIFE (Unified Procedure for Lifetime Assessment of Components and Piping in VVER NPPS during Operation) into IAEA-NULIFE Guidelines. 10:00. Deputy Head of Department of CRISM «Prometey B.Z.Margolin. Local Approach in Fracture Mechanics as Applied to Strength Analysis of NPP Equipments. 10:30. Scientific Officer for Technical and Scientific Support of TACIS/Phare, Iinstitute for Energy, JRC, European Commission R.Ahlstrand. Influence of Neutron Irradiation and Environment on the Material Properties of Internals of VVER Reactors (Authors: B.Margolin, I.Kursevitch, V.Fedorova, A.Minkin, V.Smirnov, V.Kokhonov (FSUE CRISM Prometey, St.Peterburg, Russia), V.Shamardin, V.Neustroev (NIIAR, Dimitrovgrad, Russia), G.Banyuk, V.Piminov, V.Komolov (OKB Gidropress, Podolsk, Russia), C.Martin Cerrano, J.Sainero, C.Bosh (Iberdrola), M.Navas, J.Lapena (Ciemat), P.Ortego (SEA Engineering), H.Van Rij (EC, DG-AIDCO), R.Ahlstrand (EC, DG-JRC, Institute for Energy). 11:00 11:30. Coffee break p. 8 Session 1. Material Mechanical Properties, Strength and Fracture Criteria and Limit Conditions for Structural Components. Meeting 1-3. June 16 (Wednesday). 11:30-13:30. Hall No 1. Chairmen: V.Filatov (Russia) and A.Hojna (Czech Republic) 1. Investigations of the Neutron Irradiation Effect on the Physical- Mechanical Properties of Materials for WWER Internals in the Frames of TACIS Project R2.01/02. B.Z.Margolin, I.P.Kursevich, A.J.Minkin, V.I.Smirnov, V.A.Fedorova, A.N.Lapin, V.I.Kokhonov (FSUE CRISM Prometey, St. Petersburg, Russia), V.S.Neustroev, S.V.Belozerov, V.K.Shamardin (JSC SSC RIAR, Dimitrovgrad, Russia ), V.G.Vasiliev (Concern Rosenergoatom, Moscow, Russia), R.Ahlstrand (EC, JRC, Petten, Netherlands), J.Sainero (Iberdrola Ingenieria, Madrid, Spain), M.Navas, J.Lapena (Ciemat, Madrid, Spain). 2. Behavior of 08Cr18Ni19Ti Steel after 15 Years of Operation as Core Shroud of WWER-440 Plant. A.Hojna, M.Falcnik (Nuclear Research Institute, Rez, Czech Republic), O.Hietanen, R.Korhonen (Fortum, Helsinki, Finland), L.Hulinova (NPP Dukovany, Czech Power, Czech Republic), F.Oszwald (Paks NPP, Paks, Hungary) 3. Effect of Strain and Compressive Stresses on Irradiation Swelling and Creep Strain in Cr18Ni10Ti Austenitic Steel. V.S.Neustroev, S.V.Belozerov, E.I.Makarov, Z.E.Ostrovsky (JSC SSC RIAR, Dimitrovgrad, 4. Investigation of Influence of a Neutron Irradiation on Fracture Toughness of Steel 08Cr18Ni10Ti and its Welded Joints. V.I.Smirnov, B.Z.Margolin, A.JMinkin, A.N.Lapin, V.I.Kokhonov (FSUE CRISM Prometey, St. Petersburg, 5. Analysis of Crack Growth Conditions in WWER Internals Undergone High Neutron Irradiation. B.Z.Margolin, A.A.Sorokin, V.A.Fomenko (FSUE CRISM Prometey, St. Petersburg, Russia) 6. High-Temperature Fatigue with Holdups under Specified Strains. V.M.Filatov, E.G.Yarygin (ENES, Moscow, 13:30 14:30. Lunch Meeting 1-4. June 16 (Wednesday). 14:30-18:00. Hall No 1 Chairmen: A.Varovin (Russia) and V.Kharchenko (Ukraine). p. 9 1. The Effect of Long-Term Thermal Aging on the Creep-Rupture Properties of Austenitic Steels. A.G.Gulenko, B.Z.Margolin, A.A.Buchatsky, A.D.Kashtanov (FSUE CRISM Prometey, St. Petersburg, 2. Influence of Aging under Creep on Microstructure and Properties of Pipelines and Components of NPP Equipment of the NPP Produced from austenitic Corrosion Resistant Cr-Ni Steel. M.B.Bakirov, S.V.Chubarov, I.A.Kiselev, I.A.Belunik (SCEC CMSL Ltd, Moscow, 3. The Analysis of Similarity and Distinctions in Behavior of Austenitic Cr-Ni Materials for BN and WWER NPP under Effect of Thermal Influence. I.P.Kursevich, O.Yu.Prokoshev, B.Z.Margolin, E.V.Nesterova, V.I.Smirnov, M.A.Ananieva, Yu.K.Nikolaev, V.A.Potapova (FSUE CRISM Prometey, St. Petersburg, 4. Experimental-Numerical Researches of Crack Growth Rate in Intermediate Heat Exchanger Material under Long Static Loading. A.A.Buchatsky, B.Z.Margolin, A.G.Gulenko, A.D.Kashtanov (FSUE CRISM Prometey, St. Petersburg, 5. The Calculative-Experimental Research of Creep Crack Growth for the Arc-Shaped Tension Specimen from an Alloy 45Cr26Ni33Si2Nb2 at Temperature 900 C. I.P.Popova, B.Z.Margolin (FSUE CRISM Prometey, St. Petersburg, 16:00-16:20. Coffee break 6. Structural Integrity Assessment of WWER Internals on Stress Corrosion Cracking Criterion. V.A.Fedorova, B.Z.Margolin (FSUE CRISM Prometey, St. Petersburg, Russia), V.M.Filatov (NIKIET, Moscow, 7. FE Crystal Plasticity Contribution for SCC Mechanism Understanding. A.Musienko, G.Cailletaud (St. Petersburg State Polytechnic University, St. Petersburg, Russia), T.Couvant (EDF R & D MMC, Moret-sur-Loing, France). 8. Procedure of Determination of Strength Characteristics of Irradiated Fuel Elements of Fast Neutron Reactors. M.V.Evseev, A.V.Kozlov, E.N.Shcherbakov, L.P.Sinelnikov (JSC INM, Zarechny, Russia), A.J. Minkin, A.A.Sorokin, V.N.Fomenko (FSUE CRISM Prometey, St. Petersburg, 9. Mechanisms of Fracture of Austenitic Fuel Elements Irradiated in Fast Neutron Reactors up to High Damaging Dozes. F.V.Kozlov, p. 10 I.A.Portnykh, S.A.Averin, V.L.Panchenko, M.V.Evseev (JSC INM, Zarechny, Session 2. Operation Experience and Life Time Management. Meeting 2-3. June 16 (Wednesday). 11:30-13:30. Hall No 2. Chairmen: S.Evropin (Russia) and H.Schoels (Germany). 1. Validation of BN-600 Equipment Lifetime Extension. B.A.Vasiliev, O.Yu.Vilensky, V.B.Kaidalov, Yu.L.Kamanin (JSC Afrikantov OKBM, Nizhny Novgorod, 2. The Comparative Analysis of Irradiation-Thermal Form Change for Reflectors of BN-600 Reactor (Cr18Ni9 Steel) and BN-800 Reactor (Steel Cr16Ni11Mo3). O.Yu.Vilensky, V.B.Kaidalov, D.L.Osetrov, S.A.Kapustin, V.A.Gorokhov (JSC Afrikantov OKBM, Nizhny Novgorod, 3. Using of Non-Destructive Control Techniques to Diagnose Fuel Element State of the BN-600 Reactor in JSC INM. E.N.Shcherbakov, L.P.Sinelnikov, E.A.Kinev, M.V.Evseev, V.V.Shikhslev, P.I.Yagovitin, A.A.Kuzevanov, A.V.Kozlov, V.V.Chuev, V.V.Maltsev (JSC INM, Zarechny, Russia ). 4. Ultrasonic Inspection System for Control of Base Metal and Welded Joints of BN-600 RPV. A.B.Spirkov (FSUE CRISM Prometey, St. Petersburg, 5. Peculiarities of Distribution of Surface Precipitates on Fuel Elements RBMK-1000 of the Leningrad NPP. I.M.Smirnova (JSC SSC RIAR, Dimitrovgrad, 6. Investigation of VK-50 Fuel Assembly Wrapper Material after 30 Years Operation. G.V.Filyakin, Yu.D.Goncharenko, V.K.Shamardin, Z.E.Ostrovsky (JSC SSC RIAR, Dimitrovgrad, 13:30 14:30. Lunch Meeting 2-4. June 16 (Wednesday). 14:30-18:00. Hall No 2. Chairmen: V.Yurmanov (Russia) and G.Saji (Japan) 1. Radiation Induced Long Cell (Macrocell) Corrosion in Water- Cooled Reactors of Russian Design. G.Saji (Ex-Secretary of Commission on Nuclear Safety in Japan, Yokohama, Japan). 2. Whether Development of Corrosion Defects in Heat-Exchanged Tubes of Steam Generators is Possible at Morfoline and p. 11 Ethanolamine Water-Chemistries in Secondary Systems of WWER Plants? G.P.Karzov, S.A.Suvorov, V.A.Fedorova (FSUE CRISM Prometey, St. Petersburg, 3. The Impact of Octadecylamine Microadditions into Secondary System on Corrosion Rate Reduction in WWER Steam Generators. A.N.Kukushkin, D.A.Repin (VNIIAM, Moscow, Russia), V.V.Omelchuk, LF.Barmin (Kola NPP, Poljarnye Zori, Russia), V.A.Yurmanov (NIKIET, Moscow, 4. Recent Improvements of Water Chemistry, Decontamination and Corrosion Control At Russian Design Plants With Boiling Reactors. V.A.Yurmanov, S.V.Velikopolsky, E.V.Yurmanov (NIKIET, Moscow, 5. Durability of Materials in the kinetic Theory of Strength with Accuratly Determined Parameters of Activation Volume, S.O.Ivanov ( Moscow Power Engineering Institute, Moscow, 16:00-16:20. Coffee break 6. Flow Accelerated Corrosion of Pipe Components on Nuclear Power Plants with RBMK-1000 Reactors. V.I.Baranenko, Yu.A.Yanchenko, O.M.Gulina, M.O.Ampilogov (VNIIAES, Moscow, 7. Flow Accelerated Corrosion of Direct Straight Parts of Pipelines for Nuclear Power Plants with RBMK-1000 Reactors. V.I.Baranenko, Yu.A.Yanchenko, O.M.Gulina (VNIIAES, Moscow, 8. Fatigue Crack Growth under High-Cycle Loading for 10Cr18Ni10 Steel after 180 Thousand Hours Operation. M.L.Pozdnjakov, B.Z.Margolin, V.A
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