Dismantling Techniques applied at MZFR

Size: px
Start display at page:

Download "Dismantling Techniques applied at MZFR"

Transcription

1 Wiederaufarbeitungsanlage Karlsruhe Rückbau- und Entsorgungs- GmbH The Decommissioning Project Multi-Purpose Research Reactor ( MZFR ) Dismantling Techniques applied at MZFR E. Prechtl Projekt MZFR WAK GmbH Research Reactor Decommissioning Demonstration Project (R²D²P) IAEA Workshop Decommissioning Technologies Forschungszentrum Karlsruhe 6 10 Juli

2 NPP and Prototype Reactors in Germany ( > 20 Nachhaltiger Rückbau: ( > 20 MWe ) Nuclear Facilities in the former responsibility of Karlsruhe Research Center and EWN, since July 1 st 2009: EWN NPP in Operation: 17 NPP and Prototype Reactors under Decommissioning: 15 NPP and Prototype Reactors in safe Enclosure: 3 Prototype NPP complete dismantled: 2 2

3 Decommissioning Projects on Site of the Karlsruhe Research Center ( incl. Dismantled Facilities KKN and HDR, State of Bavaria ) MZFR Multi-Purpose Research Reactor WAK (VEK) Karlsruhe Reprocessing Plant Compact Sodium- Cooled Nuclear Reactor KNK FR 2 Research Reactor Safe enclosure HDB Central Waste Treatment Department HDR Superheated Steam Reactor at Karlstein Green field KKN Niederaichbach Nuclear Power Station Green field 3

4 Multi- Purpose Research Reactor ( MZFR ): Basics Type: Power: Pressurized water reactor Heavy water moderated and cooled 200 MW th, 57 MW el (242 fuel elements) Erection: Operation: Purposes: Development and testing of nuclear materials Testing of heavy water systems Testing of fuel elements Staff training Decommissioning: Decom. Strategy: Dismantling and Removal in 8 steps (= 8 partial licences) Objective: Green field (IAEA Level 3) 4

5 MZFR Decommissioning: Fundamental Goals of Dismantling Perform the work safely (radiological and non-radiological) Dose minimization (but as low as reasonably achieviable ALARA ) Cost reduction as much as reasonably possible Waste minimization KIS - principle ( keep it simple ) 5

6 The Main Basic Objectiv: Safety Radiation Protection: workers, population, environment Technical Safety: selecting and developing dismantling techniques selecting and developing handling techniques 6

7 High Dose Rates Kontamination Typical Radiological and Non Radiological Hazards Chemical exposure: asbestos, etc. Welding and cutting: fire Operation of heavy equipment and power tools Ergonomics: heavy equipment, lifting, etc. Explosives: facility, demolition Environmental conditions: heat, cold, wet, slippery, limited visibility Confined spaces 7

8 MZFR Dismantling Technologies There is no single technique to address all dismantling boundary conditions on the MZFR decommissioning project, the techniques depends on The activity level of the systems, components and parts The selection of technologies depends also on the space conditions The physical/chemical properties of the systems and comp. to be dismantled (e.g. metal, concrete) Radioisotopes and contamination layer The type of isotopes present (Co60, H3, ) 8

9 MZFR Dismantling Technologies ( cont d ) Remote controlled dismantling (dry) for large and activated RPV components (metal): Band saw; > 500 T Autogenius burner (flame cutting under air); ~ 50 T 9

10 MZFR Dismantling Technologies ( cont d ) Remote controlled dismantling (dry) for activated metals and concrete (bioshield): RC jackhammer (excavator), with tools: ~ T 10

11 MZFR Dismantling Technologies ( cont d ) Under water remote controlled dismantling (thermal and electrical tec. for high activated metals): Plasma Cutting (UW); tool carrier, equipment: ~ T CAMC (Contact arc metal cutting (UW), adapted: ~ 100 T (without tool carrier) 11

12 MZFR Dismantling Technologies ( cont d ) Mech. hand held tools (activated and cont. metals) : Orbital saw (< 1 T ) Hydraulic cutter (~ 2 T ) Nibbler (tanks, ~ 5 T ) Angle grinder (decontamination, < 500 ) Mechanical saws (< 1 T ) 12

13 MZFR Dismantling / Decontamination Technologies Contaminated concrete: Diamant wire saw (~50 T ) Scarifier (~10 T ) Hammers drills, Comb. Hammer (> 1 T ) Air needle scaler (> 1 T ) 13

14 MZFR Plant, 1987 ( Activity Inventory approx E16 Bq ) Controlled Area Rad. Prot. Area 14

15 MZFR Plant (cont d) 1992 Controlled Area Rad. Prot. Area 15

16 MZFR Plant (cont d) 1992 Controlled Area Rad. Prot. Area 16

17 MZFR Plant (cont d) 1996 Controlled Area Rad. Prot. Area 17

18 MZFR Plant (cont d) 1998 Controlled Area Rad. Prot. Area 18

19 MZFR Plant (cont d) : Pressure test at the manufacturer s Controlled Area Rad. Prot. Area 19

20 MZFR Plant (cont d) 2001 Controlled Area Rad. Prot. Area 20

21 MZFR Plant, 2009 ( Activity Inventory approx E13 Bq ) Controlled Area Rad. Prot. Area 21

22 RPV Dismantling: Conditions at the Beginning ( Jan ) Mass: Dimensions: Geometrical Conditions: RPV Total mass approx. 403 Mg Height: 7.7 m, Ø: 4.4 m Dismantling in present position (from top to bottom and from outside to inside) Dose Rate: DL Core-inside 11 Sv/h (01/1999) Radioactivity Inventory: Approx. E 16 Bq ( key nuclide: Co-60 ) Packaging and Disposal: 178 casks and containers (104 type II Konrad containers and 74 MOSAIK casks), interim storage at the Central Waste Treatment Department (HDB) 22

23 Installations on Reactor Building Level +10 m Ventilation area Staff entrance Repository casks Packing area Ventilation Lifting, moving, and sawing RPV components Cut-off pieces Secondary waste. 2 1 Dismantling area Dismantling table Intervention area RPV lid Band saw 1: In intervention area 2: In dismantling position 23

24 Manual Dismantling of all Components above the RPV ( Dez Feb ) Dismantling of absorber rods, guiding tubes, measurement systems, etc. Criteria: dose rate < 500 µsv/h Biological Shield 24

25 Manual Dismantling of all Components above the RPV ( Dez Feb ) On the reactor lid: Cutting of measurement tubes on the RPV lid On the reactor lid: Dismantling of the absorber rod drives 25

26 Remote One-piece Removal of the Rod shaped Components inside the RPV ( April Sept ) Cooling channels, guiding tubes, etc. 272 components 212 local transfers and transports to HDB (cutting in a hot cell) Biological Shield Difficulty: 5 unremovable cooling channels 26

27 Five Unremovable Cooling Channels: Solution of the Problem Leaving in core position Planning of back-up dismantling technology: Solution: Dismantling in the underwater campaign (2004) with the hydraulic shears Typical hazard: fragmentation Biological Shield 27

28 Removal and Remote Dismantling of the RPV Lid ( Band Saw, April July 2002 ) 1: Crane 2: Support system 3: Dismantling table 4: Band saw 5: Reactor 6: Manipulator system Longitudinal section of the dismantling area in reactor building 28

29 Preparation of Removal and Remote Dismantling of the RPV Lid ( Band Saw, April July 2002 ) Dismantling of the RPV lid bolts: Cutting off the 2 bolts, that could not be loosenened 29

30 Removal and Remote Dismantling of the RPV Lid ( Band Saw, April July 2002 ) Biological Shield 30

31 Optimization of Safe Handling and Training, Trials, and Demonstration with 1:1 Dummy Part I: Pulling up, transporting, and putting down ontothebasestructure 31

32 Training, Trials, and Demonstration with 1:1 Dummy Part II: Removal of the upper filler piece with base structure to core position (in case of interventions) 32

33 Removal and Remote Dismantling of the Upper Spacer ( Band Saw, Dec April 2003 ) Upper Spacer Optimizing the type of saw band Optimizing the chip sucking system Optimizing the grippers Biological Shield 33

34 Underwater Dismantling Equipment ( Wet dismantling ) Tests and Qualifikation in an external Mock- up 40 t Dismantling Crane Bridge Manipulator Rotating Ring Drying Unit Sledge 1 with Manipulator Mast with 2 Sledges Sledge 2 with Tool Carrier and Plasma Burner 34

35 Remote Dismantling of the Moderator Tank ( RC Plasma Cutting System, Sept June 2005 ) 1. Mock-up tests with dummies Moderator Tank 2. Real remote dismantling Biological Shield 35

36 Cutting of the Remaining Five Cooling Channels under Water ( RC Hydraulic Shears,, Nov ) Cooling Channels Biological Shield 36

37 Experience with Sediments and Slag Residues Deposits and slag residues on the moderator tank bottom: Development of new tools Deposits between the upper round cover plate and stagnation sheets Optimization of the cutting process 37

38 Segmentation of the Cylindrical Wall of the Moderator Tank: Experience with the Cladding 38

39 Cleaning of the Moderator Tank Bottom before Cutting 39

40 The Importance of the Water-Purifying System Change of filter cartridges of the water-purifying system

41 RC Dismantling of the Thermal Shield ( Plasma Cutting System, July Oct ) Thermal shield ( five segments ) Biological Shield 41

42 Special Requirements for Remote Dismantling of the Thermal Shield,, Segment No. Five (cont d) Boundary conditions: Increase in wall thickness: From 70 mm up to 130 mm Gap between TS and RPV body: Only 20 mm, filled with slag and sediments No gap between TS and lower spacer (support) RPV body Thermal shield 42

43 Back-up Dismantling Technique Contact Arc Metal Cutting Cutting ( CAMC ) ( Nov ) (cont d) Teaching, Cutting, Preparation, Result: 43

44 Lifting and Remote Dismantling of the Lower Spacer ( Band Saw, Jan. - July July 2006 ) RPV body Biological Shield Lower spacer (two pieces) 44

45 Removing of the RPV Insulation Removing of the upper RPV insulation (11/2000) Removing of the lower RPV insulation (03/2007) 45

46 Dismantling of the Cylindrical Part of the RPV ( Autogenous Burner and Band Saw, June Nov ) RPV Computer RPV flange simulation Real dismantling 46

47 Dismantling of the RPV Bottom ( Band Saw, Nov. Dec ) Dismantling area RPV bottom 47

48 Mock- up dismantling equipment in the turbine hall: excavator with dismantling tools 48

49 Mock- up dismantling equipment in the turbine hall: excavator with dismantling tools (cont d) 49

50 Decontamination Work in the Pool Storage Building 50

51 Decontamination Work in the Pool Storage Building Decontamination of the recirculation ventilation shafts 51

52 Decontamination of the Concrete Shieldings 52

53 Dismantling and Decontamination in the Auxiliary Building Dismantling of the tank bases Dismantling of the 200 m 3 liquid waste tank No. 4 (of 4) Milling of the contaminated screed 53

54 Dismantling and Decontamination in the Auxiliary Building: completed areas 54

55 Waste Management: Containers, boxes and drums (for low active or contaminated waste ) 20 Container and 10 Container 200 l drum Transport boxes 55

56 Waste Management: Repository Cask Type PSC V1 ( different shieldings for low and middle active waste ) Net weight: 14.5 Mg Max. Weight: 20.0 Mg Price: T 1600 Shielding lid Concrete nozzle 1700 Wall shielding [mm]: Steel: 10 Concrete: 180 Steel: 70 56

57 Waste Management: Repository Cask Type MOSAIK ( middle activ waste ) Net weight: 8.30 Mg Load: 0.52 Mg Price: T 1060 Lead shielding: 60 / 80 mm Outer wall: cast iron with spheridiodal graphit 160 mm 1500 Lid with shielding 57

58 Waste Minimization Step 7 Remote Dismantling of the RPV incl. Internals Primary waste (disposal): Secondary waste (treatment): concept plan detail planning real (1995) (ab 1999) (2008) Tertiary waste (new installations), decont. or reuse: approx. 403 Mg approx. 95 Mg, (approx. 80 Mg contaminated water) approx. 250 Mg 58

59 Collective Dose, Steps 6 to 8 [msv] ( as of ) SG: Dismantling primary system 7.SG: Remote dismantling RPV 8.SG: Dismantling bioshield and plant decontamination Plan Real 0 6.SG 7.SG 8.SG 59

60 Collective Dose of Step 7: RC Dismantling RPV + Internals ( as of ) Plan: 1177 msv, Ist: 318 msv (27%) 60

61 Modifications / Revision Procedures under the Atomic Law (Supervisory Authority Approval) ( 01/ /2008 ) Änderungsanzeigen MZFR Gesamt / nur 7. SG von nderungsanzeigen MZFR Gesamt / nur 7 SG von hr Anzahl 40 (7. SG) Gesamt Total: Step 7 (RPV-Dis.): Anzahl Jahr 7. SG Gesamt 61

62 Comparison of MZFR Data with Those of a Reference PWR-Type Power Reactor Activity after 2.6E17 Bq defueling 3.6E16 Bq Mass of 970 Mg reactor 400 Mg pressure vessel 11,500 Mg Mass of contaminated system and installations 3,500 Mg Masses of 157,000 Mg buildings 44,000 Mg DWR: 1300 MW el MZFR: 57 MW el 62

63 Special Experience from Mock-up Testing and the Underwater Cutting Elaboration, optimization, and implementation of the dismantling concept and objectives in close cooperation with industry, university and research institutes Simulation of all cutting steps as a basis of a safe cutting procedure as well as for high availability and performance during mock-up tests and real cutting 3-D-simulation to demonstrate collision-free operation and accessibility of all cutting areas as well as implementation of locking and interlocking systems Allow sufficient time for testing and training on a mock-up Implementation of a powerful control unit for the process, parameter variations and documentation High cutting flexibility by separate use of tool carrier and manipulator system Elaboration and optimization of maintenance plan and repair strategies Short technical examination periods of documentation and equipment for all relevant cutting steps in close cooperation with the independent experts starting with mock-up testing Development of back-up techniques 63

64 MZFR Decommissioning Project: Short Summary 8 partial atomic licences: High quality of application documents New technical developments and designs necessary High activity inventory: Remote dismantling techniques (mechanical and underwater thermal dismantling techniques) Complete dismantling of the highly activated reactor Mock-ups and simulations Treatment of H3-contaminated concrete structures Expected total collective dose: < 1 man Sv Project costs: Approx. EUR 320 million 64

65 Dismantling Techniques Summary Criteria for selection of dismantling tools and techniques Staff safety Radioprotection optimization Waste minimization Cost reduction Further criteria : Installation duration Reliability Maintenance Waste minimization Replacement equipment disposability No primary criteria is the cutting speed 65

66 Conclusions Dismantling technologies are based on methods and processes applied in conventional areas Special developments and optimizations are required to fulfil special boundary conditions and to reduce the costs Remote dismantling of highly activated and contaminated RPV components is the technically most challenging step Early planning and demonstration of the interaction of the handling system and dismantling technologies in test rigs reduce the dismantling times and, hence, the costs Advanced planning tools (3D simulation, modern control and robot techniques) increase the overall system availability Experience gained from the dismantling of prototype facilities may well be used for the dismantling of industrial NPPs 66

67 The and MZFR in the Site near today Future Thank You for Your Attention! 67

Remote-Controlled Dismantling of the Thermal Isolation and Preparations for the Primary Shield Removal

Remote-Controlled Dismantling of the Thermal Isolation and Preparations for the Primary Shield Removal Remote-Controlled Dismantling of the Thermal Isolation and Preparations for the Primary Shield Removal A. Graf, J. Fleisch, S. Neff, WAK GmbH, Eggenstein-Leopoldshafen, Germany S. Klute, E. Koselowski,

More information

AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals

AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals AREVA: Experience in Dismantling and Packing of Pressure Vessel and Core Internals Jan Hendrik Bruhn GmbH/ IBRZ-G Varna, June 10 th 2010 Content General Requirements for Dismantling Projects Stade NPP

More information

Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany

Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany 861 REMOTELY-OPERATED DISMANTLING OF THE REACTOR INTERNALS AT NIEDERAICHBACH POWER PLANT USING MANIPULATORS Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany ABSTRACT The joint venture

More information

DECOMISSIONING OF THE FORMER GERMAN REPROCESSING SITE WAK STATUS OF VITRIFICATION PLANT AND DISMANTLING OF THE HLLW STORAGE TANKS

DECOMISSIONING OF THE FORMER GERMAN REPROCESSING SITE WAK STATUS OF VITRIFICATION PLANT AND DISMANTLING OF THE HLLW STORAGE TANKS DECOMISSIONING OF THE FORMER GERMAN REPROCESSING SITE WAK STATUS OF VITRIFICATION PLANT AND DISMANTLING OF THE HLLW STORAGE TANKS - 9023 J. Fleisch, M. Weishaupt, W. Pfeifer Wiederaufarbeitungsanlage Karlsruhe,

More information

RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED

RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED RESEARCH REACTOR FRJ-1 (MERLIN) THE CORE STRUCTURES OF THE REACTOR BLOCK ARE DISMANTLED B. Stahn, R. Printz, K. Matela, C. Zehbe Forschungszentrum Jülich GmbH 52425 Jülich, Germany J. Pöppinghaus Gesellschaft

More information

THE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY)

THE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY) THE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY) Hartmann, Burkhard Leushacke, Dieter F. Dr Energiewerke

More information

CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JÜLICH GMBH. H. Krumbach Forschungszentrum Jülich GmbH (FZJ) Jülich, Germany

CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JÜLICH GMBH. H. Krumbach Forschungszentrum Jülich GmbH (FZJ) Jülich, Germany WM 03 Conference, February 23-27, 2003, Tucson, AZ CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JÜLICH GMBH H. Krumbach Forschungszentrum Jülich GmbH (FZJ) 52425 Jülich, Germany ABSTRACT

More information

WM2015 Conference, March 15-19, 2015, Phoenix, Arizona, USA

WM2015 Conference, March 15-19, 2015, Phoenix, Arizona, USA An Integrated Equipment for Massive Segmentation and Packaging of Control Rod Guide Tubes 15161 Joseph Boucau*, Patrick Gobert** Sébastien Bonne *** * Westinghouse Electric Company, 43 rue de l Industrie,

More information

Best practices for preparing vessel internals segmentation projects

Best practices for preparing vessel internals segmentation projects Best practices for preparing vessel internals segmentation projects Joseph BOUCAU a*, Per SEGERUD b, Moisés SANCHEZ c a Westinghouse Electric Company, 43 rue de l Industrie, 1400 Nivelles, Belgium b Westinghouse

More information

DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE

DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE DECOMMISSIONING PROGRAMS AND TECHNOLOGY DEVELOPMENT IN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE Mitsugu Tanaka, Mimori Takeo, Takakuni Hirabayashi and Satoshi Yanagihara Japan Atomic Energy Research Institute

More information

Decommissioning three main strategies: Immediate dismantling, Safe enclosure (Deferred dismantling), Entombment

Decommissioning three main strategies: Immediate dismantling, Safe enclosure (Deferred dismantling), Entombment : Immediate dismantling, Safe enclosure (Deferred dismantling), Entombment Dr. M Knaack TÜV NORD GmbH, Hamburg / Germany Overwiew Decommissioning when and why? Law, regulations and guidelines Three main

More information

The EnBW Strategyfor Decommissioningand DismantlingofNuclearPower Plants»

The EnBW Strategyfor Decommissioningand DismantlingofNuclearPower Plants» The EnBW Strategyfor Decommissioningand DismantlingofNuclearPower Plants» 40 th MPA-Seminar Stuttgart, 6 th & 7 th October2014 Peter Daiß, EnBW Kernkraft GmbH Content 1. Introduction and Company Profile

More information

Development Status of Dismantling Technology for Old Steam Generator & RV in Kori unit 1

Development Status of Dismantling Technology for Old Steam Generator & RV in Kori unit 1 Development Status of Dismantling Technology for Old Steam Generator & RV in Kori unit 1 2016. 8. Doosan Heavy Industries & Co. Ltd Research Institute Kwang Soo Park 1 Doosan Experience 2 Development of

More information

Decommissioning Group Ketut Kamajaya

Decommissioning Group Ketut Kamajaya Decommissioning Group Ketut Kamajaya Contents of presentation Briefly history of Bandung TRIGA reactor Location of the facility Decommissioning options Characterization of System, Structure and Component

More information

References Calculation Projects

References 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 information

Optimization of Reactor Pressure Vessel Internals Segmentation in Korea

Optimization of Reactor Pressure Vessel Internals Segmentation in Korea DECOMMISSIONING AND WASTE MANAGEMENT 654 Optimization of Reactor Pressure Vessel Internals Segmentation in Korea Byung-Sik Lee 1 Introduction The decommissioning of Kori unit 1, which is the first commercial

More information

Design of Transport Container

Design of Transport Container Design of Transport Container Reduction of Occupational Exposure executing Transports of Radioactive Wastes Content 1. The Task 2. 3. Today Status 2 The Task At present there are about 4 000 drums (200

More information

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA Reactor D&D: AREVA French and German Latest Experiences - 14458 (1) Stephan Krüger, AREVA GmbH, Kaiserleistr. 29, 63067 Offenbach, Germany; stephan.krueger@areva.com (2) Xavier de Brimont, AREVA NC, 1

More information

Decommissioning of Nuclear Facilities. Waste Management

Decommissioning of Nuclear Facilities. Waste Management Decommissioning of Nuclear Facilities Waste Management Lesson Objectives Describe the requirements and methods for managing waste from decommissioning Review IAEA and US waste classification systems Review

More information

Wälischmiller Engineering

Wälischmiller Engineering Wälischmiller Engineering Cutting-Edge Technology with Tradition Wälischmiller Engineering is a specialist manufacturer of remote-handling, robotics and radiation-protection solutions for environments

More information

Benefits from R&D for D&D Projects Preparation

Benefits from R&D for D&D Projects Preparation Benefits from R&D for D&D Projects Preparation Christine GEORGES 17th February 2016 Titre du document ~ February 2016 ~ 1 SPECIAL FEATURES OF CEA D&D PROJECTS 500 M /year 800 CEA employees and about 2500

More information

Decommissioning and Site Release Problems for Georgian Nuclear Research Reactor IRT-M

Decommissioning and Site Release Problems for Georgian Nuclear Research Reactor IRT-M Decommissioning and Site Release Problems for Georgian Nuclear Research Reactor IRT-M Giorgi Nabakhtiani Grigol Kiknadze Nuclear and Radiation Safety Service Ministry of Environment Protection and Natural

More information

WM 00 conference, February 27 March 2, 2000, Tucson, AZ

WM 00 conference, February 27 March 2, 2000, Tucson, AZ WM 00 conference, February 27 March 2, 2000, Tucson, AZ REACTOR PRESSURE VESSEL REMOVAL AT A BOILING WATER REACTOR WITH SPENT FUEL IN THE ADJACENT FUEL POOL By Albert A. Freitag, WMG, Inc Greg Harttraft,

More information

ADVANCED DECOMMISSIONING COSTING CALCULATION TOOLS FOR PILOT VIENNA TRIGA MARK-II RESEARCH REACTOR

ADVANCED DECOMMISSIONING COSTING CALCULATION TOOLS FOR PILOT VIENNA TRIGA MARK-II RESEARCH REACTOR ADVANCED DECOMMISSIONING COSTING CALCULATION TOOLS FOR PILOT VIENNA TRIGA MARK-II RESEARCH REACTOR K. KRISTOFOVA, M. HORNACEK, V. SLUGEN Institute of Nuclear and Physical Engineering, Faculty of Electrical

More information

Status of the FRM-II Project at Garching. Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power Generation (KWU), D Erlangen

Status of the FRM-II Project at Garching. Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power Generation (KWU), D Erlangen IGORR7 7 th Meeting of the International Group on Research Reactors October 26-29, 1999 Bariloche, Argentina Status of the FRM-II Project at Garching Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power

More information

Planning for the Decommissioning of the ASTRA-Reactor

Planning for the Decommissioning of the ASTRA-Reactor Planning for the Decommissioning of the ASTRA-Reactor Konrad Mück, Jörg Casta Austrian Research Center Seibersdorf Introduction The ASTRA Reactor, a 10 MW multipurpose MTR research reactor at the Austrian

More information

Decommissioning, Radioactive Waste and Spent Nuclear Fuel Management in Slovakia

Decommissioning, Radioactive Waste and Spent Nuclear Fuel Management in Slovakia Decommissioning, Radioactive Waste and Spent Nuclear Fuel Management in Slovakia Presented by Mr. Vladimir Michal Division for Radiation Safety, NPP Decommissioning and RAW Management GSV, Trnava, 11 October

More information

WM 00 Conference, February 27 - March 2, 2000, Tucson, AZ

WM 00 Conference, February 27 - March 2, 2000, Tucson, AZ STATUS OF THE AVR DECOMMISSIONING PROJECT WITH SPECIAL RE- GARD TO THE INSPECTION OF THE CORE CAVITY FOR RESIDUAL FUEL ABSTRACT E. Wahlen, J. Wahl, P. Pohl Arbeitsgemeinschaft Versuchsreaktor AVR GmbH

More information

Irradiated Hardware Characterization and Packaging During Decommissioning of the Ford Nuclear Reactor at University of Michigan

Irradiated Hardware Characterization and Packaging During Decommissioning of the Ford Nuclear Reactor at University of Michigan Irradiated Hardware Characterization and Packaging During Decommissioning of the Ford Nuclear Reactor at University of Michigan A. Freitag, J. Sullivan, G.Tombari WMG, Inc. Peekskill, NY 10566 USA ABSTRACT

More information

Topical Aspects of Waste Container Approval for the Upcoming KONRAD Repository

Topical Aspects of Waste Container Approval for the Upcoming KONRAD Repository Topical Aspects of Waste Container Approval for the Upcoming KONRAD Repository ABSTRACT H. Völzke, M. Ellouz, V. Noack BAM Federal Institute for Materials Research and Testing 12200 Berlin, Germany - 10012

More information

ANSTO s POLICY for MOATA & HIFAR. Prepared by John Rowling November 2007

ANSTO s POLICY for MOATA & HIFAR. Prepared by John Rowling November 2007 ANSTO s POLICY for MOATA & HIFAR Prepared by John Rowling November 2007 Content Australian Nuclear Regulatory Systems Compare to International Recommendations Licencing Transition Period Major Issues Requirements

More information

Occupational Radiation Protection in Radioactive Waste Management

Occupational Radiation Protection in Radioactive Waste Management ISOE 2014 Asian ALARA Symposium The-K Hotel Gyeongju, Republic of Korea, 23-25 September 2014 Occupational Radiation Protection in Radioactive Waste Management 24 Sept., 2014 Byeongsoo KIM KINS 1 Contents

More information

Treatment, volume reduction and recycling of large components such as heat exchanges, steam generators and boilers

Treatment, volume reduction and recycling of large components such as heat exchanges, steam generators and boilers Treatment, volume reduction and recycling of large components such as heat exchanges, steam generators and boilers INTERNATIONAL NUCLEAR FORUM BULGARIAN NUCLEAR ENERGY NATIONAL, REGIONAL AND WORLD ENERGY

More information

Packaging for Transport of the ILW-LL of EDF First Generation Power Plant Dismantling 16517

Packaging for Transport of the ILW-LL of EDF First Generation Power Plant Dismantling 16517 Packaging for Transport of the ILW-LL of EDF First Generation Power Plant Dismantling 16517 Aurélie Brasch-Serres*, Mathias Chazot** * EDF-DP2D, 154 avenue Thiers, CS 60018, 69458 LYON CEDEX 06, FRANCE

More information

Experience and innovation. Tailored solutions for modern waste management

Experience and innovation. Tailored solutions for modern waste management Experience and innovation Tailored solutions for modern waste management The Task Currently, more than 30 countries all over the world are using controlled nuclear fission to produce electricity and are

More information

RESEARCH REACTOR DECOMMISSIONING PLAN

RESEARCH REACTOR DECOMMISSIONING PLAN RESEARCH REACTOR DECOMMISSIONING PLAN Clédola Cássia O. de Tello Pablo Andrade Grossi Brazil Contents General Aspects Ongoing Activities Decommissioning Plan Conclusion 1 TRIGA IPR-R1 REACTOR Four research

More information

Waste Management for Decommissioning of Nuclear Power Plants An EPRI Decommissioning Project Report

Waste Management for Decommissioning of Nuclear Power Plants An EPRI Decommissioning Project Report Waste Management for Decommissioning of Nuclear Power Plants An EPRI Decommissioning Project Report Rich McGrath (Presenter) - EPRI Consulting Employee Rick Reid, PhD - Senior Technical Leader Symposium

More information

Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2

Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2 General Radiation Control in the Core Shroud Replacement Project of Fukushima-Daiichi NPS Unit #2 Yasunori Kokubun, Kazuyuki Haraguchi, Yuji Yoshizawa, Yasuo Yamada Tokyo Electric Power Co, 22 Kitahara

More information

RETRIEVAL OF INTERMEDIATE LEVEL WASTE AT TRAWSFYNYDD NUCLEAR POWER STATION. I. J. Shaw, AEA Technology

RETRIEVAL OF INTERMEDIATE LEVEL WASTE AT TRAWSFYNYDD NUCLEAR POWER STATION. I. J. Shaw, AEA Technology RETRIEVAL OF INTERMEDIATE LEVEL WASTE AT TRAWSFYNYDD NUCLEAR POWER STATION ABSTRACT I. J. Shaw, AEA Technology The generation of electricity at Trawsfynydd Nuclear power station has resulted in the production

More information

OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D

OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D 16 NOVEMBER, 2011 Hiroshi RINDO JAPAN ATOMIC ENERGY AGENCY Table of Contents 1. What s happened at Fukushima Dai-Ichi NPSs

More information

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant

More information

Container Approval for the Disposal of Radioactive Waste with Negligible Heat Generation in the German Konrad Repository

Container Approval for the Disposal of Radioactive Waste with Negligible Heat Generation in the German Konrad Repository Container Approval for the Disposal of Radioactive Waste with Negligible Heat Generation in the German Konrad Repository - 12148 Holger Völzke, Gregor Nieslony, Manel Ellouz, Volker Noack, Peter Hagenow,

More information

Status of Decommissioning Preparation for Kori #1

Status of Decommissioning Preparation for Kori #1 Status of Decommissioning Preparation for Kori #1 http://www.khnp.co.kr December 6, 2017 KHNP Overview (1/2) AA (S&P), Aa2 (Moody s) KHNP Overview (2/2) Power Plants Operational status in Korea 24 22,529

More information

P. Brennecke, S. Steyer Bundesamt für Strahlenschutz Willy-Brandt-Strasse 5, D Salzgitter, Germany

P. Brennecke, S. Steyer Bundesamt für Strahlenschutz Willy-Brandt-Strasse 5, D Salzgitter, Germany WASTE CERTIFICATION, ACCEPTANCE AND DISPOSAL FOR LLW/ILW/MW/HW MANAGEMENT OF RADIOACTIVE WASTE IN GERMANY: QUALITY ASSURANCE OF WASTE PACKAGES WITH RESPECT TO IAEA RECOMMENDATIONS P. Brennecke, S. Steyer

More information

PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN

PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN PROCESS GAS WASTE HEAT BOILERS WITH THIN FLEXIBLE TUBESHEET DESIGN BORSIG The Company BORSIG Process Heat Exchanger GmbH, a member of the BORSIG Group, is the international leading manufacturer of pressure

More information

Innovative Approaches to Large Component Packaging. A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY USA

Innovative Approaches to Large Component Packaging. A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY USA Innovative Approaches to Large Component Packaging A. Freitag, M, Hooper, E, Posivak, J. Sullivan WMG, Inc. Peekskill, NY 10566 USA ABSTRACT Radioactive waste disposal often times requires creative approaches

More information

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015 Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste,12-23 October 2015 Safety classification of structures, systems and components

More information

Radioactive Waste Management at the NCSR Demokritos - Greece

Radioactive Waste Management at the NCSR Demokritos - Greece Radioactive Waste Management at the NCSR Demokritos - Greece Anastasia Savidou Radioactive Materials Management Laboratory Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, National

More information

Zion Project Overview S. Chris Baker VP EH&S

Zion Project Overview S. Chris Baker VP EH&S Zion Project Overview S. Chris Baker VP EH&S 1 Agenda Asset Sale Agreement Organization Nuclear Decommissioning Process Overview of Zion Station Decommissioning Schedule Near Term Activities Spent Fuel

More information

WM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA

WM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA Modular Design of Processing and Storage Facilities for Small Volumes of Low and Intermediate Level Radioactive Waste including Disused Sealed Sources - 12372 David R. Keene*, Susanta Kumar Samanta** and

More information

WM'99 CONFERENCE, FEBRUARY 28 - MARCH 4, 1999 RESEARCH REACTOR DECOMMISSIONING POTENTIAL BACK END OPTIONS

WM'99 CONFERENCE, FEBRUARY 28 - MARCH 4, 1999 RESEARCH REACTOR DECOMMISSIONING POTENTIAL BACK END OPTIONS RESEARCH REACTOR DECOMMISSIONING POTENTIAL BACK END OPTIONS ABSTRACT M England, BNFL, Risley, Warrington, Cheshire, England As with all nuclear facilities, research reactors will, at some stage, reach

More information

Development of Decommissioning Plan in Indonesia

Development of Decommissioning Plan in Indonesia Development of Decommissioning Plan in Indonesia Endang Kurnia and Berthie Isa R²D ²P: Review of a Decommissioning Plan Bucharest, Romania, 4-8 July 2011 IAEA International Atomic Energy Agency Legal and

More information

SAFETY ANALYSIS AND ENVIRONMENTAL IMPACT ASSESSMENT FOR FOTON RTC DECOMMISSIONING

SAFETY ANALYSIS AND ENVIRONMENTAL IMPACT ASSESSMENT FOR FOTON RTC DECOMMISSIONING SAFETY ANALYSIS AND ENVIRONMENTAL IMPACT ASSESSMENT FOR FOTON RTC DECOMMISSIONING S.V. Komarov, A.Z. Gaiazov, A.A. Rozhnovskaia, I.V. Kuzmin, O.E. Polovnikov Sosny Research and Development Company (Sosny

More information

CUTTING TECHNIQUES FOR FACILITIES DISMANTLING IN DECOMMISSIONING PROJECTS. Paulo E. O. Lainetti 1 ABSTRACT

CUTTING TECHNIQUES FOR FACILITIES DISMANTLING IN DECOMMISSIONING PROJECTS. Paulo E. O. Lainetti 1 ABSTRACT 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 CUTTING TECHNIQUES FOR

More information

DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES. R. Papp Forschungszentrum Karlsruhe GmbH P.O. Box 36 40, D Karlsruhe

DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES. R. Papp Forschungszentrum Karlsruhe GmbH P.O. Box 36 40, D Karlsruhe WM 02 Conference, February 24-28, 2002, Tucson, AZ- pg. 1 DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES R. Papp Forschungszentrum Karlsruhe GmbH P.O. Box 36 40, D-76021 Karlsruhe

More information

Radioactive Waste Management and Environmental Surveillance at KANUPP. Khawaja Ghulam Qasim Sr. Manager (KANUPP)

Radioactive Waste Management and Environmental Surveillance at KANUPP. Khawaja Ghulam Qasim Sr. Manager (KANUPP) Radioactive Waste Management and Environmental Surveillance at KANUPP Khawaja Ghulam Qasim Sr. Manager (KANUPP) PAEC Nuclear Power Program K-1 C-1 C-2 C-3 C-4 K-2/K-3 1972 2000 2011 Sep.2016 2017 2021

More information

European Experience In Transport / Storage Cask for Vitrified Residues

European 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 information

C. Kennes - C. Mommaert - M. Van haesendonck (Bel V) H. Libon - A. De Backer (Belgonucleaire) Decommissioning of Belgonucleaire MOX plant

C. Kennes - C. Mommaert - M. Van haesendonck (Bel V) H. Libon - A. De Backer (Belgonucleaire) Decommissioning of Belgonucleaire MOX plant C. Kennes - C. Mommaert - M. Van haesendonck (Bel V) H. Libon - A. De Backer (Belgonucleaire) Decommissioning of Belgonucleaire MOX plant Content Regulatory framework Strategy Status of the project Role

More information

Decommissioning plans for TVO's new reactors

Decommissioning plans for TVO's new reactors Decommissioning plans for TVO's new reactors Decommissioning and dismantling, Studsvik, September 14 th -16 th 2010 Contents Introduction: present situation of construction and licencing of OL3 and OL4

More information

TROJAN DECOMMISSIONING STATUS. OPUC Meeting March 8, 2005 (draft)

TROJAN DECOMMISSIONING STATUS. OPUC Meeting March 8, 2005 (draft) TROJAN DECOMMISSIONING STATUS OPUC Meeting March 8, 2005 (draft) 1 Meeting Agenda Trojan Decommissioning Overview History Major Projects Overall Performance Remaining Major Activities Current Issues USDOE

More information

BN-1200 Reactor Power Unit Design Development

BN-1200 Reactor Power Unit Design Development International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) BN-1200 Reactor Power Unit Design Development B.A. Vasilyev a, S.F. Shepelev a, M.R.

More information

CONSTOR SPENT NUCLEAR FUEL STORAGE AND TRANSPORT CASK SYSTEM

CONSTOR 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 information

Renovating a Medical Radiosotope Production Hot Cell T. GROCHOWSKI ROBATEL Technologies

Renovating a Medical Radiosotope Production Hot Cell T. GROCHOWSKI ROBATEL Technologies Renovating a Medical Radiosotope Production Hot Cell - 11337 T. GROCHOWSKI ROBATEL Technologies D. SANCHETTE & S. COLLONGE ROBATEL Industries Rue de Genève, 69740 Genas - France P. Van boxem National Institute

More information

HOW R&D MAY HELP TO IMPROVE RP PERFORMANCE AT THE DECOMMISSIONING STAGE OF NUCLEAR POWER PLANT?

HOW R&D MAY HELP TO IMPROVE RP PERFORMANCE AT THE DECOMMISSIONING STAGE OF NUCLEAR POWER PLANT? HOW R&D MAY HELP TO IMPROVE RP PERFORMANCE AT THE DECOMMISSIONING STAGE OF NUCLEAR POWER PLANT? Gérard Laurent, EDF DIN CIDEN, France Ludovic Vaillant, CEPN, France ISOE Symposium, Rio, May 2015 CONTENT

More information

PLAN FOR MOATA REACTOR DECOMMISSIONING, ANSTO

PLAN FOR MOATA REACTOR DECOMMISSIONING, ANSTO PLAN FOR MOATA REACTOR DECOMMISSIONING, ANSTO Sungjoong (Shane) KIM Australian Nuclear Science and Technology Organisation New Illawarra Road, Lucas Heights, N.S.W., 2234, Australia Email: skx@ansto.gov.au

More information

Advanced Technologies for Fuel Debris Retrieval towards Fukushima Daiichi Decommissioning

Advanced Technologies for Fuel Debris Retrieval towards Fukushima Daiichi Decommissioning Advanced Technologies for Fuel Debris Retrieval towards Fukushima Daiichi Decommissioning Eiichiro WATANABE Waste Technology Section Division of Nuclear Fuel Cycle and Waste Technology Department of Nuclear

More information

Heavy Component Replacement in Nuclear Power Plants

Heavy Component Replacement in Nuclear Power Plants Heavy Component Replacement in Nuclear Power Plants Steve Sills, Vice President Business Development, SGT Darren Wood, Manager Component Replacements, AREVA Purpose and Process Goal Recent successes and

More information

Decommissioning Planning

Decommissioning Planning Decommissioning Planning Ingemar Lund - Swedish Radiation Protection Authority, SSI, Sweden IAEA Regional Workshop: Legal and Regulatory Aspects of Decommissioning of Research Reactors Manila, Philippines,

More information

Safety Research for the Disposal of Radioactive Waste Generated by Decommissioning of of Nuclear Power Facilities

Safety Research for the Disposal of Radioactive Waste Generated by Decommissioning of of Nuclear Power Facilities Safety Research for the Disposal of Radioactive Waste Generated by Decommissioning of of Nuclear Power Facilities Kenkichi ISHIGURE Japan Radioisotope Association 1 Decommissioning of nuclear power facilities

More information

STORAGE OF SPENT NUCLEAR FUEL IN MVDS OF PAKS NPP

STORAGE OF SPENT NUCLEAR FUEL IN MVDS OF PAKS NPP Technical section STORAGE OF SPENT NUCLEAR FUEL IN MVDS OF PAKS NPP Zoltán Huszák, János Bencze Fuel Handling Machine Operator Paks NPP, Hungary 1. INTRODUCTION Four VVER-440/213 type reactors operate

More information

Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors)

Module 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 information

SPENT FUEL STORAGE IN BELGIUM

SPENT FUEL STORAGE IN BELGIUM SPENT FUEL STORAGE IN BELGIUM R. Vermeyen Tractebel Energy Engineering Belgatom 1. Introduction The Belgian utility Electrabel presently operates 7 PWR nuclear power plants, distributed over two sites

More information

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant 8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100

More information

3.8 Radioactive Waste Management (RWM) Status in Thailand

3.8 Radioactive Waste Management (RWM) Status in Thailand 3.8 Radioactive Waste Management (RWM) Status in Thailand The "Atom for Peace" program was launched after the end of the World War II. This stimulated the concepts of having an atomic energy research center

More information

Spanish Management Issues in Radioactive and Nuclear Waste Materials Dr. Amparo González Espartero

Spanish Management Issues in Radioactive and Nuclear Waste Materials Dr. Amparo González Espartero Spanish Management Issues in Radioactive and Nuclear Waste Materials Dr. Amparo González Espartero Senior Researcher Head of CIEMAT Quality Management CYTED- Energy Area Technical Secretary of Spanish

More information

Gap 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 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 information

Dry storage systems and aging management

Dry 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 information

Radiation Protection Challenges associated with the dismantling of Nuclear Power Plant

Radiation Protection Challenges associated with the dismantling of Nuclear Power Plant Radiation Protection Challenges associated with the dismantling of Nuclear Power Plant Ludovic Vaillant ISOE International Symposium Rio de Janeiro, May 2015 Context (1/2) For various reasons - economical,

More information

Joint ICTP-IAEA School on Nuclear Energy Management. 15 July - 3 August, Lecture Notes. I. Mele IAEA, Vienna, Austria

Joint ICTP-IAEA School on Nuclear Energy Management. 15 July - 3 August, Lecture Notes. I. Mele IAEA, Vienna, Austria 2473-9 Joint ICTP-IAEA School on Nuclear Energy Management 15 July - 3 August, 2013 Lecture Notes I. Mele IAEA, Vienna, Austria The IAEA Nuclear Energy Management School ICTP, Trieste, 15-2 August 2013

More information

TOPICAL SESSION MANAGEMENT OF DECOMMISSIONING WASTES

TOPICAL SESSION MANAGEMENT OF DECOMMISSIONING WASTES TOPICAL SESSION MANAGEMENT OF DECOMMISSIONING WASTES Waste Technology Section WATEC 2004, 18-22 Oct 2004 Presentation Objectives Highlight the interactions between decommissioning and waste management

More information

CAREM Prototype Construction and Licensing Status

CAREM Prototype Construction and Licensing Status IAEA-CN-164-5S01 CAREM Prototype Construction and Licensing Status H. Boado Magan a, D. F. Delmastro b, M. Markiewicz b, E. Lopasso b, F. Diez, M. Giménez b, A. Rauschert b, S. Halpert a, M. Chocrón c,

More information

Regulatory Approach to Radiation Protection in new NPPs in Finland

Regulatory Approach to Radiation Protection in new NPPs in Finland Regulatory Approach to Radiation Protection in new NPPs in Finland ISOE European Workshop in Prague 20.-22. 6. 2012 Veli Riihiluoma Radiation and Nuclear Safety Authority (STUK) RADIATION AND NUCLEAR SAFETY

More information

Steam Power Station (Thermal Station)

Steam Power Station (Thermal Station) Steam Power Station (Thermal Station) A generating station which converts heat energy into electrical energy through turning water into heated steam is known as a steam power station. A steam power station

More information

Topics on Current Nuclear Regulation in Japan

Topics on Current Nuclear Regulation in Japan Topics on Current Nuclear Regulation in Japan Commissioner Toyoshi Fuketa Nuclear Regulation Authority(NRA 26 th Annual Regulatory Information Conference Bethesda North Marriott Hotel & Conference Center

More information

0 SUMMARY 4. 1 INTRODUCTION AND METHOD Purpose Method Scope and Assumptions Scope Assumptions 12

0 SUMMARY 4. 1 INTRODUCTION AND METHOD Purpose Method Scope and Assumptions Scope Assumptions 12 Page 2 of 24 CONTENTS 0 SUMMARY 4 1 INTRODUCTION AND METHOD 4 1.1 Purpose 4 1.2 Method 5 1.3 Scope and Assumptions 6 1.3.1 Scope 6 1.3.2 Assumptions 12 2 BACKGROUND 13 2.1 Present situation in Norway 13

More information

Decommissioning Worldwide and NEA Activities

Decommissioning Worldwide and NEA Activities Decommissioning Worldwide and NEA Activities Claudio Pescatore - Ivo Tripputi NEA Principal Administrator - NEA CPD Management Board Chair WM Symposia, Phoenix, 2-6 March 2014 Decommissioning: what does

More information

Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency

Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident Ryodai NAKAI Japan Atomic Energy Agency Contents Introduction Japanese Government Report to the IAEA

More information

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams Reactor Technology: Materials, Fuel and Safety Dr. Tony Williams Course Structure Unit 1: Reactor materials Unit 2. Reactor types Unit 3: Health physics, Dosimetry Unit 4: Reactor safety Unit 5: Nuclear

More information

GENERAL CONTENTS SECTION I - NUCLEAR ISLAND COMPONENTS

GENERAL CONTENTS SECTION I - NUCLEAR ISLAND COMPONENTS - June 2013 Addendum GENERAL CONTENTS SECTION I - NUCLEAR ISLAND COMPONENTS SUBSECTION "A" : GENERAL RULES SUBSECTION "B" : CLASS 1 COMPONENTS SUBSECTION "C" : CLASS 2 COMPONENTS SUBSECTION "D" : CLASS

More information

Development of technologies for the processing and disposal of radioactive waste

Development of technologies for the processing and disposal of radioactive waste Development of technologies for the processing and disposal of radioactive waste International Experts' Symposium on the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Plant Unit 1-41 March

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT

UNITED 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 information

MEXT Nuclear Energy R&D

MEXT Nuclear Energy R&D Tokyo, 1 th November 2011 MEXT Nuclear Energy R&D Masaaki NISHIJO Director, Office for Nuclear Fuel Cycles, Ministry of Education, Culture, Sports, Science and Technology (MEXT) 1 Future Nuclear Energy

More information

Best Practice Form. Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site:

Best Practice Form. Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site: Best Practice Form Best Practice Title: Open Air Demolition of Asbestos Gunite by Using Track Mounted Wet Cutting Saw DOE Site: Lawrence Livermore National Laboratory (LLNL) Facility Name: B328 Demolition

More information

Angra 3 Current status and challenges to continue

Angra 3 Current status and challenges to continue Angra 3 Current status and challenges to continue Vienna February 2017 Introduction Brazilian Transmission Network Integrated electric power system: continental dimensions Manaus Fortaleza Itaipu Brasília

More information

Welding Units and Understanding Statements

Welding Units and Understanding Statements Course #: IT72 Grade Level: 9-12 Course Name: Welding II Level of Difficulty: Average Prerequisites: None # of Credits: 2 semesters 1 credit The following is a Career and Technical Education (CTE) class

More information

Collection and safekeeping of TRIGA Spent Nuclear Fuel

Collection and safekeeping of TRIGA Spent Nuclear Fuel Collection and safekeeping of TRIGA Spent Nuclear Fuel Presented by Ken Whitham, US DOE-ID and Jim Floerke, CH2MWG Idaho 2013 Spent Nuclear Fuel at the Idaho Cleanup Project 2 Atoms for Peace Since the

More information

WM'00 Conference, February 27 - March 2, 2000, Tucson, AZ DECOMMISSIONING OF FOUR GERMAN FUEL CYCLE FACILITIES

WM'00 Conference, February 27 - March 2, 2000, Tucson, AZ DECOMMISSIONING OF FOUR GERMAN FUEL CYCLE FACILITIES DECOMMISSIONING OF FOUR GERMAN FUEL CYCLE FACILITIES Dr. Helmut Rupar, Roland Baumann, Peter Faber, Dr. Manfred Ruhbaum, Helmut Schmitt Siemens AG, Power Generation Group (KWU), Germany ABSTRACT The decommissioning

More information

Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed

Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed William D. Magwood, IV Director General Nuclear Energy Agency International Workshop on Decommissioning of Nuclear Power Plants

More information

Developing Technologies for Nuclear Fuel Cycles

Developing Technologies for Nuclear Fuel Cycles Developing Technologies for Nuclear Fuel Cycles Hitachi Review Vol. 48 (1999), No. 5 277 Radioactive Waste Treatment and Spent Fuel Storage Makoto Kikuchi, Ph.D. Takuma Yoshida Masami Matsuda, Ph.D. Hidetoshi

More information

NUCLEAR. Nuclear Reactor Pressure Vessel Seals

NUCLEAR. Nuclear Reactor Pressure Vessel Seals NUCLEAR Nuclear Reactor Pressure Vessel Seals SEALING CONCEPT Technetics Group is the world s leading manufacturer of Nuclear Reactor Pressure Vessel (RPV) Closure Head Seals. In addition, Technetics Group

More information