Bulatom Conference June 2017 Ludek Urban & Vit Sousek. ŠKODA JS Casks for SNF & HAW
|
|
- Junior Bishop
- 6 years ago
- Views:
Transcription
1 Bulatom Conference June 2017 Ludek Urban & Vit Sousek ŠKODA JS Casks for SNF & HAW
2 Company profile ŠKODA JS a.s. is more than 60 years a longtime reliable supplier of technologies for nuclear power industry. Its main business activities include engineering, the production of components and the provision of services for nuclear power plants. In the past sixty years, ŠKODA JS has supplied primary equipment not only for nuclear power plants in the Czech Republic and Slovakia, but also in Hungary, Bulgaria, Germany, Russia, China and Finland. ŠKODA JS is a supplier of spent fuel transport and storage casks and casks for radioactive waste for more than 20 years Company ŠKODA founded 1956 ŠKODA begins its nuclear power activities 1961 Commencement of manufacturing of equipment for A-1 nuclear power plant in Jaslovské Bohunice, Slovakia Start of the VVER reactor program 60 years anniversary of ŠKODA JS 2
3 Strategic Business Units Engineering EPC projects Construction of VVER (VVER) nuclear power units Deliveries and modernization of I&C of nuclear power plant units Calculation analyses for nuclear power plants Designing activities Pipeline systems in power engineering Owner s Engineer activities Spent fuel interim storage facilities Construction of research and teaching reactors Decommissioning 3 Production Equipment for VVER (WWER) and RBMK (LWGR) nuclear power plants Equipment for PWR and BWR nuclear power plants Equipment for research reactors Spent nuclear fuel storage equipment Services Control of reactor hall equipment shutdowns Reactor hall equipment maintenance and repairs Reactor hall equipment modernization Control/extension of reactor hall equipment service life In-service inspections of reactor hall main equipment Designer s supervision in reactor inspections and repairs VVER (WWER) and RBMK (LWGR) drive tests Spare parts and consumables
4 References ŠKODA JS manufactured and delivered i.a. equipment: 21 complete VVER 440 reactors 3 complete VVER 1000 reactors (one reactor originally supplied to Belene NPP is now operable at unit 4, Kalinin NPP, Russia) 1143 control rod drive mechanisms for VVER 440 reactors 1240 linear stepping drives for VVER 1000 reactors VVER 440 compact spent fuel storage racks 6820 stored fuel assemblies VVER 1000 compact spent fuel storage racks 4911 stored fuel assemblies 414 spent fuel transport and storage casks and casks for radioactive waste 4
5 Spent Fuel Casks Spent Fuel Transport and Storage Casks Manufactured by ŠKODA JS Designed by GNS in cooperation with ŠKODA JS Designed by ŠKODA JS Over 400 casks manufactured since
6 Casks Designed by GNS in cooperation with ŠKODA JS CASTOR 440/84 Cask Dukovany NPP (Czech Republic) 60 pcs delivered in EWN Greifswald (Germany) 21 pcs supplied in KWO Obrigheim (Germany) 12 pcs supplied in 2012 CASTOR 440/84 M Cask Cask body GNS design Basket - ŠKODA JS design Dukovany NPP (Czech Republic) 25 pcs supplied in pcs suppl. by 2016 acc. to GNS licence 12 pcs to be delivered by
7 Casks Designed by GNS CASTOR HAW 20/28 CG Cask GNS design Reference 42 casks delivered to GNS (Gesselschaft für Nuklear-Service) End users: Gösgen Nuclear Power Plant NOK (Nordostschweizerische Kraftwerke) KFZ (Forschngszentrum Karlsruhe) 7
8 Casks Designed by GNS in cooperation with ŠKODA JS CONSTOR 440/84 Cask Body GNS design basket ŠKODA JS design 34 casks for Kozloduy NPP, Bulgaria (supplied in 2009) For Storage only (no Transport) 8
9 Casks Designed by GNS CONSTOR RBMK 1500 Cask GNS design 98 casks for Ignalina NPP, Lithuania CONSTOR RBMK 1500 M2 Cask GNS design Ignalina NPP, Lithuania 33 pcs manufactured in pcs to be delivered 9
10 Casks Designed by GNS CASTOR 1000/19 cask for VVER 1000 GNS design Cask production for Temelín NPP, supplies: 17 casks in casks to be manufactured by
11 Casks Designed by ŠKODA JS ŠKODA 1000/19 Cask Dual-purpose cask for transport and long term dry storage of spent fuel of the type VVER 1000 with enrichment of up to 5 wt% U 235. Contract Signed in 2015 Totaly 58 pcs to be delivered by 2035 License By SUJB in 03/
12 Casks Designed by ŠKODA JS 1. Cask Body Steel forging with inserted neutron shielding in form of PE-rods. Cask body surface is mantled with cooling ribs ensuring transfer of residual heat to ambient environment. Cask outer surface is covered with anticorrosion coating. Sealing surfaces are plated with welded stainless steel and then machined. Inner cavity walls are coated with metal alloy. 12
13 Casks Designed by ŠKODA JS 2. Lids Ensuring Tightness of Inner Cask Space Cask innner space is hermeticaly closed with 2 stainless steel lids, both with two gaskets. Cask tightness is permanently monitored using pressure transducers. 3. Trunions for Cask Handling The Cask is equipped with 4 trunions in upper part for cask handling and with 2 trunions for tilting from/to upright position. Trunions are made of stainless steel forgings, they are bolted to the cask body. 13
14 Casks Designed by ŠKODA JS 4. Fuel Basket ŠKODA 1000/19 Basket consists of 19 hexagonal tubes made of aluminum alloy with B 4 C content. Boron contained in Al-alloy ensures neutron absorption and thus the subcriticality of the inserted fuel. Aluminum rods inserted in corners of hexagonal tubes ensure better basket stability at the dynamic strain. The tubes are bolted together. Basket capacity is 19 FA. Bottom of the basket is fixed with the closing plate. 14
15 Casks Designed by ŠKODA JS 5. Shock Absorbers Both ends of the cask are equipped with shock absorbers at the transport (part of the transport vehicle) in order to preserve the cask against damage at the postulated 9 m drop. AAAAAAAA 15
16 Casks Designed by ŠKODA JS Technical Parameters: Fuel type VVER 1000 Fuel enrichment up to 5 wt% U 235 Average Burn-up 70 MWd/kgU Basket capacity 19 FAs Cask body material forged steel Total mass in storage config. 119 t Outer diameter 2341 mm Inner diameter 1482 mm Height w/o shock absorbers 5497 mm Height of inner shaft 4622 mm Total heat capacity 21,5 kw Maximum surface temperature 85 C Max. dose rate at cask surface 1 msv/h Max. dose rate at 2 m distance 0,1 msv/h 16
17 Casks Designed by ŠKODA JS ŠKODA 440/84 Cask Designated for transport and long term dry storage of spent fuel of the type VVER 440 with enrichment up to 5 wt% U 235. Contract Signed in 2016 Up to 89 pcs to be delivered by 2048 License Application By SUJB in 12/
18 Casks Designed by ŠKODA JS Basic Structural Parts 1. Cask body 2. Lids ensuring tightness of inner cavity 3. Trunions for handling 4. Fuel basket ŠKODA 440/84 E 5. Shock absorbers 18
19 Casks Designed by ŠKODA JS Fuel Basket ŠKODA 440/84 Basket consists of 85 hexagonal tubes made of aluminum alloy. Wedge shaped plates of austenitic steel inserted among hex. tubes ensure better basket stability at the dynamic strain. Boron contained in wedges ensures neutron absorption and thus the subcriticality of the whole assembly. Basket capacity is 84 FA. The central tube remains empty. Model of Fuel Basket ŠKODA 440/84 19
20 Casks Designed by ŠKODA JS Technical Parameters: Fuel type VVER 440 Fuel enrichment up to 5 wt% U 235 Average Burn-up 60 MWd/kgU Basket capacity 84 FAs Cask body material forged steel Total mass in storage config. 120 t Outer diameter 2640 mm Inner diameter 1740 mm Height w/o shock absorbers 4250 mm Height of inner shaft 3260 mm Total heat capacity 30 kw Maximum surface temperature 85 C Max. dose rate at cask surafce 1 msv/h Max. dose rate at 2 m distance 0,1 msv/h 20
21 Casks Designed by ŠKODA JS ŠKODA VPVR/M Cask ŠKODA JS original design for transport and storage of the research reactor spent nuclear fuel Project supported by DoE (USA) and IAEA in the frame of RRRFR program (Russian-origin Research Reactor Fuel Return) Licence in CZ, RF 6 casks for NRI Rez 10 casks for IAEA Already used in: Czech Rep. Bulgaria Hungary Poland Georgia Uzbekistan Vietnam Romania Serbia Belarus 21
22 Casks Designed by ŠKODA JS Type VTUK cask for Ignalina NPP For transport of partly used fuel between two RBMK 1500 units Detail design by ŠKODA JS Customer ETV, Lithuania 12 m length Supplied in February
23 Casks Designed by ŠKODA JS Cask ŠKODA UOS VVER 440 for a long term Deposition Double-casing with NiCr hot spray Outer Casing 55 mm made of low doped alloy Steel Inner Casing 5 mm Stainless Steel Built-in Structure made of AlMgSi 0,5 23
24 Spent Fuel Casks Review of References Customer Scope of supply End user Country Pcs NRI Rez Chernobyl NPP K1 x IRTM NRI Rez Czech Republic 1 ŠKODA VPVR/M NRI Rez, IAEA Czech Republic 16 Cask wagon Chernobyl NPP Ukraine 1 CASTOR 440/84 EWN Greifswald Germany 21 CASTOR 440/84 Dukovany NPP Czech Republic 60 GNS CASTOR 440/84 M Dukovany NPP Czech Republic 36 CASTOR 1000/19 Temelin NPP Czech Republic 8 CASTOR 440/84 mvk Obrigheim NPP Germany 12 CASTOR HAW 20/28 Gösgen NPP, NOK GNS Gorleben Forschungszentrum Karlsruhe Switzerland Germany 42 CASTOR V/21 Virginia Power USA 4 CASTOR THTR GNS, Gorleben Germany 33 GNS 16 GRC Petten the Netherlands 2 CONSTOR 440/84 Kozloduy NPP Bulgaria 34 CONSTOR RBMK 1500 Ignalina NPP Lithuania 98 CONSTOR RBMK 1500 M2 Ignalina NPP Lithuania 33 ETB VTUK Ignalina NPP Lithuania 1 Updated: January 4, 2017 Total (since 1993)
25 Special Purpose Casks Type TC1 cask for Megapie experimental project Designed by ŠKODA JS to transport an irradiated target, filled with melted lead and bismuth, to Zwilag storage facility Customer: Paul Scherrer Institute, Villigen, Switzerland Parameters: Diameter 1,1 m Length 6 m Weight 40 t Supplied in January
26 Special Purpose Casks PETA Container (P6, SB-260L, SB-160T) Designed by ŠKODA JS for transport and storage of nuclear emitters Customer: GAMMA Service, Germany 4 pcs supplied in Type KSV 440 Container Designed by ŠKODA JS for transport of RPV steel surveillance samples Reference Mochovce NPP/Units 3,4 (2011) 26
27 Special Purpose Casks ŠKODA JS design Review of References Scope of supply Customer Country Year Pcs End user KSV 440 Container - for RPV steel surveillance specimens (VVER 440) TKSV 1000 Container - for RPV steel surveillance specimens (VVER 1000) ŠKODA PRAHA Czech Republic ŠKODA PRAHA Czech Republic Type A Package - for fresh fuel ČEZ Czech Republic KNI Container - for fragmented in-core neutron flux measurement detectors IK Container - for ex-core ionisation chambers PETA6/P6 Container - for medical purposes PETA6/SB 160 T - for medical purposes PETA6/SB 260 L - for medical purposes TC 1 transport cask - for irradiated target with eutectic of Pb+Bi mixture KSV 440 Container - for RPV steel surveillance specimens (VVER 440) 300 TERA - for transport of iradiated specimens ŠKODA PRAHA Czech Republic ŠKODA PRAHA Czech Republic ÚJP Zbraslav Czech Republic Gamma Service Radeberg Gamma Service Radeberg Paul Scherrer Institut Villigen Germany Germany Switzerland ŠKODA SLOVAKIA Slovakia ÚJP Zbraslav Czech Republic Total 12 Mochovce NPP/1,2 Slovakia Temelin NPP, Czech Republic Temelin NPP, Czech Republic Temelin NPP, Czech Republic Temelin NPP, Czech Republic Gamma Service Radeberg, Germany Gamma Service Radeberg, Germany Gamma Service Radeberg, Germany Paul Scherrer Institut Villigen, Switzerland Mochovce NPP/3,4 Slovakia CV Řež, Czech Republic 27
28 Special Purpose Casks ŠKODA JS design Casks for high activated waste from decommissioning ŠKODA 360 Special purpose cask for Dummy Fuel Assemblies and/or Absorbing Followers of Control Assemblies ŠKODA 300 & ŠKODA 180 Special purpose casks for interim storaging of parts from Reactor Core Internals Main Features Height DN Wall Thickness Primary Lid Closing Plate 4147 mm 2580 mm acc. to loaded activity bolted welded 28
29 PWR & BWR Equipment Spent Fuel Cask Transfer Facility FA3 Flamanville NPP/Unit 3 (EPR reactor) ŠKODA JS s own design Scope - basic & detail design, fabrication, installation, setting into operation Customer: Electricité de France Contract award December 2007 Supplied in
30 Current Key Project - Casks Cask wagon for the Chernobyl NPP, Ukraine ŠKODA JS s design Design, manufacture, supply, installation and certification Cask with a length of 12 m, designed for transporting 9 special spent fuel assemblies from the reactor RBMK Transport wagon with hydraulic equipment for cask lifting Supply of 1 set in
31 Safety Requirements Safety Requirements Basic safety ensured through cask design as a package type B(U)F acc. to TS-R-1 (SSR-6) and ADR Main criteria: Subcriticality Shielding Tight enclosure Thermal conditions Transport Drop from 9 m Pin drop from 1 m Pressure test 200 m (2 Mpa) for 1 h Fire test 800 C for 30 min. Storage Fall from 0,3 m Fire test 600 C for 1 h 31
32 Cask Design Engineering Capabilities: - Research & Development - Basic Design - Design Reports Calculations - Safety Analysis Report - Design Documentaion - Drawings - Specifications - Manufacturing & Technology - Type Approval - Oper. & Maintenance Manual - Commissioning Plans ŠKODA VPVR/M Cask 32
33 Safety Analysis & Safety Documentation Safety Analysis & Safety Documentation (PSAR, SAR) Subcriticality calculations Shielding calculations - Radioactive inventory Thermal calculations Strenght analysis - Transport and storage regimes under normal and accidental conditions Supporting calculations - cask loadings with combinations of varies fuel parameters - analyses of terorists attack 33
34 Drop Test Real Drop Test Simulation of Drop Test 34
35 Quality Assurance ISO 9001: 2015 ISO 14001: 2015 (ЕMS) OHSAS 18001: 2007 ASME-Code Section III, Div.1 (stamps N, NPT, certificate NS) nuclear equipment ČSN-EN-ISO nuclear equipment welding AD-2000 Merkblatt HP 0, DIN class D (Germany) TRV 006 (TÜV, Germany) manufacture of nuclear equipment B-type casks ABOS (Paks NPP, Hungary) nuclear equipment RCCM (France) CEFRI (France) HAF604 35
36 Contact Thank you for your attention ŠKODA JS a.s. Orlik Plzeň Czech Republic Tel.: GSM:
Current reactor technology, part III: Radek Škoda Czech Technical University Prague WNU SI 2010 Christ Church, Oxford
Current reactor technology, part III: VVER RBMK Radek Škoda Czech Technical University Prague Christ Church, Oxford 1 Overview 1. Gen 1-2-3-4 2. Reactor technology: RBMK 3. Reactor technology: VVER 4.
More informationCONSTOR SPENT NUCLEAR FUEL STORAGE AND TRANSPORT CASK SYSTEM
CONSTOR SPENT NUCLEAR FUEL STORAGE AND TRANSPORT CASK SYSTEM Dr. Ralf Peters, Managing Director, GNB Dr. Rudolf Diersch, Research and Development, GNB Mr. Allen Jack, International Sales Department, GNB
More informationTechnological Solutions of SF Storage in the World
Technological Solutions of SF Storage in the World 1. ACTUAL TRENDS OF SF MANAGEMENT In the previous decades, the nuclear industry has gathered a lot of experience in operation of nuclear power plants
More informationLong-Term Interim Storage of Spent Nuclear Fuel and HAW in Dual Purpose Casks Perspectives and Challenges
Long-Term Interim Storage of Spent Nuclear Fuel and HAW in Dual Purpose Casks Perspectives and Challenges Outline: Bundesanstalt für Materialforschung und prüfung (Federal Institute for Materials Research
More informationKarel Böhm 1, Milan Brumovsky 2, Jirí Zd árek 2 ABSTRACT
Karel BOHM, SUBJ (Czech Republic) Milan BRUMOVSKY, Jirí ZD ÁREK, Nuclear Research Institute (Czech Republic) Integrated surveillance specimen programme for WWER-1000/V-320 reactor pressure vessels Karel
More informationПРЕДПРИЯТИЕ ГОСКОРПОРАЦИИ «РОСАТОМ» STATE CORPORATION "ROSATOM GROUP OF COMPANIES
ПРЕДПРИЯТИЕ ГОСКОРПОРАЦИИ «РОСАТОМ» STATE CORPORATION "ROSATOM GROUP OF COMPANIES Development Program of Cask Technologies for Management of Spent Fuel Assemblies from Russian NPPs as Means of Harmonization
More informationNEW DUAL-PURPOSE CASK CASTOR MTR 3 FOR DISPOSAL OF SPENT FUEL FROM RESEARCH REACTORS
NEW DUAL-PURPOSE CASK CASTOR MTR 3 FOR DISPOSAL OF SPENT FUEL FROM RESEARCH REACTORS Leonard Synder, Christian Heß, Johannes M. Graf GNS Gesellschaft für Nuklear-Service mbh Frohnhauser Straße 67, 45127
More informationTrend of SFM and Storage in Eastern Europe Ferenc Takáts
Trend of SFM and Storage in Eastern Europe Ferenc Takáts TS Enercon Kft. Budapest, Hungary E-mail: (takats@tsenercon.hu) Structure Introduction Number of NPPs SF facilities SF amounts Individual country
More informationWWER-440 CONTROL ASSEMBLY LOCAL POWER PEAKING INVESTIGATION ON LR-0 REACTOR
International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 WWER-440 CONTROL ASSEMBLY LOCAL POWER PEAKING INVESTIGATION ON LR-0
More information40. MPA-Seminar. Updated management of spent fuel from the perspective of the German industry
40. MPA-Seminar Updated management of spent fuel from the perspective of the German industry 6./7. October 2014 R. Hüggenberg, Dr. Th. Funke 40. MPA-Seminar 6./7. October 2014 / Hü - 1 Content 1. Introduction
More informationEuropean Experience In Transport / Storage Cask for Vitrified Residues
ABSTRACT European Experience In Transport / Storage Cask for Vitrified Residues L. Blachet, C. Otton, D. Sicard AREVA TN International Because of the evolution of burnup of spent fuel to be reprocessed,
More informationNUCLEAR POWER DELIVERIES. Ing. Martin Pecina, MBA General director VÍTKOVICE POWER ENGINEERING a. s ATOMEX Prague
Ing. Martin Pecina, MBA General director VÍTKOVICE POWER ENGINEERING a. s. 25. 26. 10. 2011 ATOMEX Prague We are the most significant Central European machinery group with strong position in selected segments
More informationInventory Prediction and BUC Calculations Related to MEU/LEU IRT Fuels of LVR-15 Research Facility
Inventory Prediction and BUC Calculations Related to MEU/LEU IRT Fuels of LVR-15 Research Facility L. Markova, F. Havluj, M. Marek Nuclear Research Institute at Rez, Czech Republic International Workshop
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationDry storage systems and aging management
Dry storage systems and aging management H.Issard, AREVA TN, France IAEA TM 47934 LESSONS LEARNED IN SPENT FUEL MANAGEMENT Vienna, 8-10 July 2014 AREVA TN Summary Dry storage systems and AREVA Experience
More informationGreifswald Project Introduction/Experience summary Axel Bäcker
Decommissioning operation of large decommissioning projects 20 years experience Decommissioning management of five power reactors on the Greifswald site Greifswald Project Introduction/Experience summary
More informationDemonstration Test Program for Long term Dry Storage of PWR Spent Fuel
Demonstration Test Program for Long term Dry Storage of PWR Spent Fuel 16 November 2010 K.Shigemune, The Kansai Electric Power Co., Inc. The Japan Atomic Power Company Kyushu Electric Power Co., Inc. Mitsubishi
More informationCurrent Status of Interim Storage Facility for Spent Fuels in Japan
Current Status of Interim Storage Facility for Spent Fuels in Japan 19-21 May 2014, IAEA workshop for DPC Tatsuya Ishikawa Cask Procurement Group, Engineering Department Recyclable-Fuel Storage Company
More informationGap Analysis Examples from Periodical Reviews of Transport Package Design Safety Reports of SNF/HLW Dual Purpose Casks
Gap Analysis Examples from Periodical Reviews of Transport Package Design Safety Reports of SNF/HLW Dual Purpose Casks Steffen Komann a*, Frank Wille a, Bernhard Droste a a Federal Institute for Materials
More informationReferences Calculation Projects
Karl-Heinz-Beckurts-Straße 8 D-52428 Jülich Tel. (+49) 02461-933-0 References Calculation Projects Wissenschaftlich-Technische Ingenieurberatung GmbH Karl-Heinz-Beckurts-Str. 8, 52428 Jülich Tel.: +49
More informationAir Transport of Spent Nuclear Fuel (SNF) Assemblies. M.J. Haire, S.D. Moses Oak Ridge National Laboratory Oak Ridge, TN, USA
Air Transport of Spent Nuclear Fuel (SNF) Assemblies M.J. Haire, S.D. Moses Oak Ridge National Laboratory Oak Ridge, TN, 37381-6166 USA V.I. Shapovalov, A. Morenko All-Russian Scientific Research Institute
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationDemonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High Corrosion-resistant
14th International Symposium on the Packaging and Paper # 149 Transportation of Radioactive Materials (PATRAM 24), Berlin, Germany, September 2-24, 24 Demonstrative Drop Tests of Transport and Storage
More informationAvailable online at ScienceDirect. Procedia Engineering 86 (2014 )
Available online at www.sciencedirect.com ScienceDirect Procedia Engineering 86 (2014 ) 308 314 1st International Conference on Structural Integrity, ICONS-2014 Guidelines for Integrity and Lifetime Assessment
More informationHEU REMOVAL FROM POLAND ABSTRACT
HEU REMOVAL FROM POLAND BOLSHINSKY I., MOSES S., TYACKE M. Idaho National Laboratory Idaho Falls, Idaho, USA KRZYSZTOSZEK G. National Center for Nuclear Research Swierk, Poland CHOLERZYNSKI A. Radioactive
More informationAGING MECHANISMS INFLUENCE ON TRANSPORT SAFETY OF DUAL PURPOSE CASKS FOR SPENT NUCLEAR FUEL. Bernhard Droste, Frank Wille, Steffen Komann
AGING MECHANISMS INFLUENCE ON TRANSPORT SAFETY OF DUAL PURPOSE CASKS FOR SPENT NUCLEAR FUEL Bernhard Droste, Frank Wille, Steffen Komann BAM Federal Institute for Materials Research and Testing Berlin,
More informationAging Management of Dual-Purpose Casks on the Example of CASTOR KNK
Aging Management of Dual-Purpose Casks on the Example of CASTOR KNK Iris Graffunder a (*), Ralf Schneider-Eickhoff b and Rainer Nöring b a EWN Energiewerke Nord GmbH, Lubmin, Germany b GNS Gesellschaft
More informationThe following considerations are taken into account for designing the NUHOMS MP197 packaging.
14th International Symposium on the Packaging and Paper # 164 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 NUHOMS - MP197 Transport Cask Peter Shih, TRANSNUCLEAR,
More informationMECHANICAL ASSESSMENT CRITERIA OF SPENT FUEL ASSEMBLIES BASKET DESIGN. Christian Kuschke Viktor Ballheimer Frank Wille Steffen Komann
MECHANICAL ASSESSMENT CRITERIA OF SPENT FUEL ASSEMBLIES BASKET DESIGN Christian Kuschke Viktor Ballheimer Frank Wille Steffen Komann BAM Federal Institute for Materials Research and Testing, Berlin, Germany
More informationNuclear Power Development in Europe: Rosatom perspective
ROSATOM Nuclear Power Development in Europe: Rosatom perspective Alexey Kalinin Head, International Business, Rosatom CEO, Rusatom Overseas Platts 7 th Annual European Nuclear Conference June 25-26, 2012
More informationAn optimized cask technology for conditioning, transportation and long term interim storage of «End of Life» nuclear waste
An optimized cask technology for conditioning, transportation and long term interim storage of «End of Life» nuclear waste Gilles Clément 17th February 2016 Titre du document ~ February 2016 ~ 1 Waste
More informationSPENT FUEL REPATRIATION FROM SERBIA
SPENT FUEL REPATRIATION FROM SERBIA O. Šotić Public Company Nuclear Facilities of Serbia International Conference on Research Reactors Safe Management and Effective Utilization Rabat November 2011 Contents
More informationDisposal Of Spent Fuel In Salt Using Borehole Technology: BSK 3 Concept
IYNC 2008 Interlaken, Switzerland, 20 26 September 2008 Paper No. 154 Disposal Of Spent Fuel In Salt Using Borehole Technology: BSK 3 Concept Stefan Fopp 1, Reinhold Graf 1, Wolfgang Filbert 2 1 GNS Gesellschaft
More informationSpent Fuel Management in Slovakia
Spent Fuel Management in Slovakia Juraj Václav Nuclear Regulatory Authority of the Slovak Republic International Conference on Management of Spent Fuel from Nuclear Power Reactors 31 May 4June2010 Vienna,
More informationWWER Fuel Performance and Modelling Activities in Bulgaria
WWER Fuel Performance and Modelling Activities in Bulgaria Maria Manolova INRNEBAS, Sofia, Bulgaria manolova@inrne.bas.bg TWGFTP Meeting Vienna, IAEA, 2729 29 April 2010 Intermediate Meeting of the TWGFTP,
More informationF. Boldt, K. Hummelsheim, M. Péridis, F. Rowold, M. Stuke. Safety of long-term dry storage in Germany - Challenges and Perspectives
F. Boldt, K. Hummelsheim, M. Péridis, F. Rowold, M. Stuke Safety of long-term dry storage in Germany - Challenges and Perspectives Outline Current and future situation of spent fuel in Germany Central
More informationINPP Workshop on Reactor Dismantling. Jörg Viermann, GNS Gesellschaft für Nuklear-Service mbh
INPP Workshop on Reactor Dismantling Jörg Viermann, GNS Gesellschaft für Nuklear-Service mbh GNS Gesellschaft für Nuklear-Service mbh Competence for Nuclear Services A medium-sized company founded in 1974,
More informationManaging severe accidents beyond design conditions (SAM) Vladivoj REZNIK, Engineering Director
Managing severe accidents beyond design conditions (SAM) Vladivoj REZNIK, Engineering Director International Power Summit, Munich February 2014 Slovenské elektrárne, subsidiary of Enel Enel world presence
More informationATOMEX Prague. I&C SYSTEMS ZAT a.s.
ATOMEX 25-26.10.2011 Prague I&C SYSTEMS ZAT a.s. CZECH REPUBLIC & NUCLEAR The Czech Republic is one of the European countries able to design, construct and safely operate nuclear power plants with the
More informationPrepared by: ŠKODA JS a.s. Consultancy, design and production: AKCENT s.r.o. 2
ACTIVITY REPORT 2015 Prepared by: ŠKODA JS a.s. Consultancy, design and production: AKCENT s.r.o. 2 CONTENTS 02 Opening Word from the Chairman of the Board of Directors and General Director 04 Company
More informationEnsa Solutions for Interim Dry Spent Fuel Storage & Transportation
ENSA (Grupo SEPI) Ensa Solutions for Interim Dry Spent Fuel Storage & Transportation INMM 31 st Spent Fuel Management Seminar January 12, 2016, Washington DC, USA Alejandro Palacio Design & Licensing Dpt.
More informationActivity Report 2016
Activity Report 2016 Prepared by: ŠKODA JS a.s. Consultancy, design and production: AKCENT s.r.o. Contents 02 Foreword by the Chairman of the Board of Directors and General Director 06 Company Introduction
More informationLight Water Reactor in Russia
ROSATOM STATE CORPORATION ON NUCLEAR ENERGY ROSATOM Light Water Reactor in Russia Presented M.A.Bykov OKB GIDROPRESS 17 th TWG-LWR Meeting, Vienna, 18-20 June 2012 NPP Electricity Generation in Russia
More informationRenaissance of the Nuclear Power Industry. Activity Report 2008
Renaissance of the Nuclear Power Industry Activity Report 2008 MISSION STATEMENT To be a reliable and trustworthy partner responding to all customers requirements and needs. To meet their expectations
More informationRadioactive Waste Packaging of Conditioned Waste at Kozloduy NPP Site. G. Genchev, D. Dimov RW Treatment Plant Kozloduy NPP 3321 Bulgaria
Radioactive Waste Packaging of Conditioned Waste at Kozloduy NPP Site G. Genchev, D. Dimov RW Treatment Plant Kozloduy NPP 3321 Bulgaria K. Russev VIT Ferro-Concrete Elements Production PLC Bulgarian Aviation
More informationThe paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date.
14th International Symposium on the Packaging and Paper # 108 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 NAC's Modular, Advanced Generation, Nuclear All-purpose
More informationYa.I.Shtrombakh. «Russian nuclear power plants life time management» Finnish Nuclear Society s seminar: "Nuclear Russia today and tomorrow"
Ya.I.Shtrombakh «Russian nuclear power plants life time management» Finnish Nuclear Society s seminar: "Nuclear Russia today and tomorrow" Helsinki 2009 Main directions of RRC Kurchatov institute activities
More informationCORROSION MONITORING SYSTEM IN THE SLOVAK REPUBLIC NUCLEAR POWER PLANTS
CORROSION MONITORING SYSTEM IN THE SLOVAK REPUBLIC NUCLEAR POWER PLANTS M. Brezina, L. Kupca VUJE Inc. Okruzna 5, 918 64 Trnava, Slovak Republic Email address of main author: brezina@vuje.sk Abstract.
More informationFEED BACK ON THE USE OF THE MX6 MOX FUEL TRANSPORT CASK: REDUCTION OF THE DOSE UPTAKE DURING OPERATIONS. Laurent BLACHET, Thierry LALLEMANT,
FEED BACK ON THE USE OF THE MX6 MOX FUEL TRANSPORT CASK: REDUCTION OF THE DOSE UPTAKE DURING OPERATIONS Laurent BLACHET, Thierry LALLEMANT, TN International, AREVA Group, 1, rue des Hérons 78180 MONTIGNY
More informationVVER-440/213 - The reactor core
VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there
More informationThe Research Reactor IRT-Sofia 50 years after first criticality
The Research Reactor IRT-Sofia 50 years after first criticality KIRIL KREZHOV KREZHOV@inrne.bas.bg Bulgarian Academy of Sciences - Institute for Nuclear Research and Nuclear Energy Nuclear Scientific Experimental
More informationUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 72-1040 HI-STORM UMAX Canister Storage System Holtec International, Inc. Certificate of Compliance
More information1 Introduction and object of the statement Request of advice of the BMU Consultations Assessment basis Statement...
Note: This is a translation of the statement entitled Anforderungen an bestrahlte Brennelemente aus entsorgungstechnischer Sicht. In case of discrepancies between the English translation and the German
More informationWM2016 Conference, March 5 10, 2016, Phoenix, Arizona, USA. Perspective of Dry Interim Storage of spent nuclear fuel (SNF) in Germany
Perspective of Dry Interim Storage of spent nuclear fuel (SNF) in Germany ABSTRACT Christoph Gastl and Julia Palmes Federal Office of Radiation Protection According to article 6 of the German Atomic Energy
More informationNuclear Reactors. 3 Unit Nuclear Power Station - Coastal Bryon Nuclear Plant, Illinois. 3 Unit Nuclear Power Station - Desert
3 Unit Nuclear Power Station - Desert Nuclear Reactors Homeland Security Course February 1, 2007 Tom Gesell 3 Unit Nuclear Power Station - Coastal Bryon Nuclear Plant, Illinois 1 Power Reactor Statistics
More informationIAEA-TECDOC Spent fuel management: Current status and prospects 1997
IAEA-TECDOC-1006 Spent fuel management: Current status and prospects 1997 Proceedings The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies The originating Section
More informationRegulatory framework on DPC licensing in the Czech Republic. Peter Lietava
Regulatory framework on DPC licensing in the Czech Republic Peter Lietava 1 Content Czech regulatory framework on DPC licensing Interfaces between DPC, AFR storage facilities and NPP licensing and transport
More informationSteam Generator Ageing Management in Slovakia current practices and related issues
International Atomic Energy Agency Meeting on Update and Upgrade of IAEA-TECDOC on Ageing Management of Steam Generators IAEA, Vienna, 15 18 June 2009 Steam Generator Ageing Management in Slovakia current
More informationShipment of Spent Nuclear Fuel from the Nuclear Research Institute Rez plc, Czech Republic to the Russian Federation for Reprocessing
Shipment of Spent Nuclear Fuel from the Nuclear Research Institute Rez plc, Czech Republic to the Russian Federation for Reprocessing - 9422 J. Podlaha Nuclear Research Institute Rez plc Husinec-Rez 130,
More information1.INTRODUCTION. I.BOLSHINSKY Idaho National Laboratory (INL), Idaho Falls, ID, USA
E5 THE SHIPMENT OF RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT AND FRESH NUCLEAR FUEL FROM BELARUS AND DELIVERY OF FRESH LOW ENRICHED URANIUM NUCLEAR FUEL TO BELARUS S. SIKORIN, S. MANDZIK, S. POLAZAU,
More informationManufacturability, safety, reliability and efficiency
Manufacturability, safety, reliability and efficiency VVER reactor plant, related to a group of multi-loop plants, was initially designed as a six-loop plant and then evolved to a fourloop plant. In VVER
More informationSafety reassessment of WWR-K RR related to HEU/LEU conversion and feedback from accident at the Fukushima-Daiichi NPP
2017 IGORR Conference, 4 to 7 December 2017, Sydney, Australia, Safety reassessment of WWR-K RR related to HEU/LEU conversion and feedback from accident at the Fukushima-Daiichi NPP Murat Tulegenov Institute
More informationGeneric Aspects for Dismantling Preparation of INPP Reactor Facilities. Aleksej Merežnikov, Ignalina NPP, July 2014
Generic Aspects for Dismantling Preparation of INPP Reactor Facilities Aleksej Merežnikov, Ignalina NPP, July 2014 Agenda INTRODUCTION REGULATORY FRAMEWORK RBMK-1500 FEATURES GENERAL APROACH STATUS AND
More informationRosatom Global Expertise in NPP Construction
ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM Rosatom Global Expertise in NPP Construction Nuclear Industry Localization Conference Cape Town, June 1-3, 2011 Fully Integrated Nuclear Technology Company
More informationLe eccellenze italiane nello scenario internazionale
Le eccellenze italiane nello scenario internazionale Giornata di studio AIN 2012 Roma, 10 maggio 2012 Enel/ATN The Enel Group Nuclear Assets Nuclear Policy ATN Area Tecnica Nucleare The Slovak Project
More informationRUSSIA S CURRENT AND FUTURE NUCLEAR BUSINESS STRATEGIES & NUCLEAR EXPORT POLICIES
RUSSIA S CURRENT AND FUTURE NUCLEAR BUSINESS STRATEGIES & NUCLEAR EXPORT POLICIES International Uranium Enrichment Center Russian Federation JAEA, 12-13 December,2012 TODAY ROSATOM SHARES: 16% of the electricity
More informationRosatom Seminar on Russian Nuclear Energy Technologies and Solutions
ROSATOM STATE ATOMIC ENERGY ОАО CORPORATION «ТВЭЛ» - российский ROSATOM производитель ядерного топлива Nuclear fuel for VVER-1200 Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions L.T.
More informationManagement of Spent Fuel from the Perspective of the German Industry
Management of Spent Fuel from the Perspective of the German Industry Dipl.-Ing. W. Graf GNS Gesellschaft für Nuklear- Service mbh IAEA Vienna International Conference on Management of Spent Fuel from Nuclear
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR VVER REACTORS Ondřej Novák 1, Martin Ševeček 1,2 1 Department of Nuclear Reactors, Faculty of Nuclear
More informationJADROVÁ A VYRAĎOVACIA SPOLOČNOSŤ
JADROVÁ A VYRAĎOVACIA SPOLOČNOSŤ 01 JAVYS safely with every step JAVYS THE MISSION Safe, reliable, economically effective and efficient operation and decommissioning of nuclear facilities Safe, reliable,
More informationNuclear Science for Sustainable Environment and Security
Nuclear Science for Sustainable Environment and Security JRC and INRNE Joint Activities Recent Results Excellence, Sustainability, Integration Jordan Stamenov, Boyko Vachev Advanced Technologies and Methods
More informationReactor plant for NPP WWER-1000
2008 Key assets to support a strategic choice NPPs with WWER-type reactors (WWER-440,, WWER-1200) in operation and under construction Evolutionary, safe and innovative design ÔÔ reactor plant is a reactor
More informationPRESENT STATUS OF LEGAL & REGULATORY FRAMEWORK AND DECOMMISSIONING PLANNING FOR DNRR. Prepared by NUCLEAR RESEARCH INSTITUTE, VAEC.
TECHNICAL MEETING ON THE RESEARCH REACTOR DECOMMISSIONING DEMONSTRATION PROJECT: CHARACTERIZATION SURVEY PHILIPPINES, 3 7 DECEMBER 2007 PRESENT STATUS OF LEGAL & REGULATORY FRAMEWORK AND DECOMMISSIONING
More informationCONVERSION OF THE GHANA'S MINIATURE NEUTRON SOURCE REACTOR FROM HEU TO LEU: 2017 REPORT
CONVERSION OF THE GHANA'S MINIATURE NEUTRON SOURCE REACTOR FROM HEU TO LEU: 2017 REPORT H. C. ODOI, J. K. GBADAGO, W. OSEI-MENSAH, E. O. AMPONSAH-ABU, K.GYAMFI, E. SHITSI, A. G. AMPONG, R. E. QUAGRAINE
More informationInterim Storage of Spent Fuel in Germany History, State and Prospects
Interim Storage of Spent Fuel in Germany History, State and Prospects J. Palmes, C. Gastl Federal Office for Radiation Protection Bundesamt für Strahlenschutz International Conference on Management of
More informationNPP Construction in Russia and abroad
ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM Rosatom Engineering & Construction Division NPP Construction in Russia and abroad DMITRI VYSOTSKI Head of Strategy Director, International Business Development
More informationCurrent Status of Decommissioning in Lithuania
Current Status of Decommissioning in Lithuania Dr. Gintautas Poškas Researcher Lithuanian Energy Institute Nuclear Engineering Laboratory Nuclear facilities in Lithuania Ignalina NPP (under decommissioning)
More informationONE GROUP - MANY POSSIBILITIES
MTG incorporates leading Bulgarian foundries, specialized in casting and machining of parts of aluminium, cast iron and steel. The major technologies adopted and utilized by the plants include: centrifugal
More informationTransport Experience of New "TNF-XI" Powder Package
14th International Symposium on the Packaging and Paper # 099 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 Transport Experience of New "TNF-XI" Powder Package
More informationCompany Details. Leeds, UK Sofia, Bulgaria (HQ) Istanbul, Turkey. Hanoi, Vietnam
COMPANY BRIEF Company Details Leeds, UK Sofia, Bulgaria (HQ) Istanbul, Turkey Hanoi, Vietnam Established in 1992 Private ownership Staff: 150 Certificates: ISO 9001:2008 ISO 14001:2004 BS OHSAS 18001:2007
More informationPreparation of NPP Dukovany Periodic Safety Review
Preparation of NPP Dukovany Periodic Safety Review Dubský Ladislav Petr Vymazal Nuclear Research Institute Řež plc., Czech Republic ČEZ, a.s., Nuclear Division, Dukovany NPP, Czech Republic 1. ABSTRACT
More informationWM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA
The New TN MW Cask System Focused on Facilities End-of-Life Waste Management 16627 Jay Thomas *, Sandrine Toupiol *, Bruno Dumont * Florence Lefort-Mary **, Gilles Clément**, Christine Lamouroux ** * AREVA
More informationThe Mutual Influence of Materials and Thermal-hydraulics on Design of SCWR Review of Results of the Project HPLWR Phase 2
Institute of Nuclear Technology and Energy Systems The Mutual Influence of Materials and Thermal-hydraulics on Design of SCWR Review of Results of the Project HPLWR Phase 2 J. Starflinger, T. Schulenberg
More informationReview of Generation III Reactors
Review of Generation III Reactors Dr. Helmut Hirsch Scientific Consultant for Nuclear Safety Neustadt, Germany 1 Status of Nuclear Power Today (I) Future of nuclear power uncertain. No significant growth
More informationManufacture of Spent Fuel and High Level Waste. Uve Günther, Dr. Manfred Baden, TÜV Rheinland Group, Berlin, Germany
Official i Monitoring i of the Quality Assurance in the Manufacture of Spent Fuel and High Level Waste Transport and Storage Casks Uve Günther, Dr. Manfred Baden, TÜV Rheinland Group, 10882 Berlin, Germany
More information{ POWER OF ALLIANCE } ALLIANCE OF CZECH SUPPLIERS FOR NUCLEAR POWER PLANTS
{ POWER OF ALLIANCE } ALLIANCE OF CZECH SUPPLIERS FOR NUCLEAR POWER PLANTS z.s. (CPIA) EXPORT COORDINATOR OF CZECH DELIVERIES FOR NUCLEAR POWER PLANTS CPIA was established in September 2015 as a non-exclusive
More informationSPENT FUEL REPATRIATION FROM THE REPUBLIC OF SERBIA
Invited Paper E1 SPENT FUEL REPATRIATION FROM THE REPUBLIC OF SERBIA O. ŠOTIĆ Public Company "Nuclear Facilities of Serbia," Belgrade, Republic of Serbia Abstract During the RA research reactor s nearly
More informationSpent Fuel Management and Research Activities in Korea
Spent Fuel Management and Research Activities in Korea 33 rd Spent Fuel Management Seminar (January 23 ~ 25, 2018, Alexandria, VA) Woo-seok Choi Director of RAM Transport and Storage Dep t Contents 1.
More informationH.R relies on the NRC for all safety issues. However, the NRC provides limited safety evaluations.
To Elected Officials and others: August 15, 2017 Shimkus Bill H.R. 3053, The Nuclear Waste Policy Amendments Act of 2017 makes nuclear waste problems worse. Vote NO on H.R. 3053 because it: Eliminates
More informationGlobal Threat Reduction Initiative. Defense Nuclear Nonproliferation
Global Threat Reduction Initiative GTRI Removal Program Overview December 3, 2014 1 GTRI Removal Program Overview GTRI s mission is to reduce and protect vulnerable nuclear and radiological materials at
More informationProfile LFR-23 COLONRI I. CZECH Republic
Profile LFR-23 COLONRI I CZECH Republic GENERAL INFORMATION NAME OF THE COnvection LOop NRI I FACILITY ACRONYM COLONRI I COOLANT(S) OF THE PbBi FACILITY LOCATION (address): CVR, Hlavni 130 250 68 Husinec-Rez
More informationBULGARIAN COUNTRY NUCLEAR POWER PROFILE
BULGARIAN COUNTRY NUCLEAR POWER PROFILE Albena Georgieva Bulgarian Nuclear Regulatory Agency Department of International Co-operation phone: + 359 2 9406 943 fax: + 359 2 9406 919 e-mail: A.Georgieva@bnra.bg
More informationMONTE CARLO METHODS APPLICATION TO CANDU SPENT FUEL COMPARATIVE ANALYSIS
Romanian Reports in Physics, Vol. 56, No. 4, P. 721-726, 2004 MONTE CARLO METHODS APPLICATION TO CANDU SPENT FUEL COMPARATIVE ANALYSIS &$05*($18 1), T. ANGELESCU 2), P. ILIE 1) 1) Institute for Nuclear
More informationSpent Fuel Storage Operational Experience With Increased Crud Activities. I. Barnabás Public Agency for Radioactive Waste Management (PURAM), Hungary
Spent Fuel Storage Operational Experience With Increased Crud Activities I. Barnabás Public Agency for Radioactive Waste Management (PURAM), Hungary T. Eigner Paks NPP, Hungary I. Gresits Technical University
More informationTransportability of Dual Purpose Casks in Germany
Transportability of Dual Purpose Casks in Germany - Situation and Perspective - Frank Wille BAM Federal Institute for Materials Research and Testing Berlin, Germany IAEA International Workshop on Dual
More informationHTR-PM Project Status and Test Program
IAEA TWG-GCR-22 HTR-PM Project Status and Test Program SUN Yuliang Deputy Director, INET/ Tsinghua University March 28 April 1, 2011 1 Project organization Government INET R&D, general design, design of
More informationCzech Industry Cooperation with Rosatom CZECH INDUSTRY CAPABILITIES FOR ROSATOM NUCLEAR POWER PLANTS UNDER CONSTRUCTION
Czech Industry Cooperation with Rosatom CZECH INDUSTRY CAPABILITIES FOR ROSATOM NUCLEAR POWER PLANTS UNDER CONSTRUCTION DEEP HISTORY OF COOPERATION NPP Number and type of reactors Present state Bohunice
More informationLight years ahead! AREVA TN Americas 1/22/2015. Prakash Narayanan AREVA TN INMM Spent Fuel Management January 2015
Light years ahead! Prakash Narayanan AREVA TN INMM Spent Fuel Management January 2015 Established in 1965 to transport nuclear materials in the U.S. AREVA TN manages globally more than 6,000 shipments
More informationRussian Research Reactor Spent Nuclear Fuel Repatriation from the Reactor Country to the Russian Federation for Reprocessing 14149
Russian Research Reactor Spent Nuclear Fuel Repatriation from the Reactor Country to the Russian Federation for Reprocessing 14149 Karel Svoboda, Josef Podlaha, Frantisek Svitak UJV Rez, a. s. ABSTRACT
More informationEQUIPMENT FOR REPAIR OF RBMK-1500 FUEL ASSEMBLIES OF IGNALINA NPP
EQUIPMENT FOR REPAIR OF RBMK-1500 FUEL ASSEMBLIES OF IGNALINA NPP S.Stravinskas, G.Pashkevichius, I.Krivov, G.Krivoshein Engineers, Nuclear-Physics Laboratory, NSD Ignalina NPP 1. INTRODUCTION The Ignalina
More information