ITER Remote Handling: Overview and Technical Requirements

Similar documents
EU Contribution to ITER Remote Handling

ITER REMOTE HANDLING SYSTEM

ITER Remote Maintenance

Europe s contribution to ITER Remote Handling

TOKAMAK ARCHITECTURE FOR PRACTICAL REMOTE MAINTENANCE

THE EUROPEAN IN KIND CONTRIBUTION TO THE ITER REMOTE MAINTENANCE SYSTEM

ITER Vacuum Vessel Status and Procurement

ITER Assembly Opportunities

DTT FLEXIBILITY: VV, DIVERTOR, FW AND REMOTE HANDLING ISSUES. G. Di Gironimo on behalf of DTT team

INFORMATION DAY. Fusion for Energy (F4E)

The ITER Neutral Beam Test Facility. Design Overview. European Tasks ref. TW3-THHN-IITF1 ( ) TW4-THHN-IITF2 ( ) Jean-Jacques Cordier

4 JET Operations. 4 JET Operations 4.1 INTRODUCTION 4.2 INSTALLATION OF NEW COMPONENTS

Occupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations

ITER Organization. Procurement Process Industrial Strategy Business Opportunities

Convergence of Design and Fabrication Methods for ITER Vacuum Vessel and In-vessel Components

Call for Nomination. Vacuum Vessel Assembly Welding

ITER R&D Needs, Challenges, and the Way Forward

ITER Organization. Françoise Flament. Head of Procurement Arrangements & Contracts Division. Journée ITER/CEA 01/12/2010. Page 1

Technical Specifications (In-Cash Procurement)

ITER Status & Opportunities. Meeting with CONFINDUSTRIA Piemonte Torino, November 16 th 2015 Benjamin Perier

Technical Specifications (In-Cash Procurement)

Technical Summary for the Tokamak Assembly Works- A0

5 th INTERNATIONAL CONFERENCE ON THE FRONTIERS OF PLASMA PHYSICS AND TECHNOLOGY April 21, 2011, Singapore

Hot Cell Complex Building Engineering Contract (REVISED)

R&D required to place a test module on FNF (how does it compare to ITER TBM?) R&D required for base blanket

Remote Maintenance Topic Summary

3.6 Site Layout and Buildings

Specific technologies involved Near term opportunities for Industry Future opportunities for Industry (hints)

Technical Summary. Contract for Procurement of Piping and Fittings (IO/14/CFT/9560/ACS CP/1)

Wendelstein 7-X A technology step towards DEMO

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

Pre-conceptual Design Assessment of DEMO Remote Maintenance

Integrated System Level Simulation and Analysis of DEMO with Apros. Sami Kiviluoto

Technical Summary for TCC0 Global overview of the scope for TCC0 contract

FUSION FOR ENERGY The European Joint Undertaking for ITER and the Development of Fusion Energy

Key Features and Progress of the KSTAR Tokamak Engineering

K. Jayarajan Division of Remote Handling and Robotics Bhabha Atomic Research Centre

Maintenance Duration Estimate for a DEMO Fusion Power Plant, based on the EFDA WP12 Pre-Conceptual Studies

3ème RV Business du Nucléaire Civil en PACA. ITER Organization Future Call for Tenders

Safety Classification of Mechanical Components for Fusion Application

Technical Summary. 1. Purpose

Design Analysis for the development of the design of the ITER Hot Cell Complex (HHC)

Plasma Research Center, University of Tsukuba Y. Nakashima, GAMMA 10 Group

DTP2 Verifying The Divertor Remote Handling Equipment For ITER

Replacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head

Tokamak KTM Complex for Material Investigation

FABRICATION DESIGN AND CODE REQUIREMENTS FOR THE ITER VACUUM VESSEL

Status of Design and Research & Development for ITER Sector Sub-assembly Tools

Recent Progress of GIS/GDC Design and Manufacturing for ITER

Technical Specification - Hot Cell Complex - Mechanical Engineering

14.1 Functions, Basic Configuration and System Boundaries

EU Contribution to ITER Fuel Cycle

Fusion: the fundamental principle

ITER Fuelling System Design and Challenges Gas and Pellet Injection and Disruption Mitigation

Fusion Nuclear Science Facility (FNSF) low Q mission range & prerequisites options in associated research program for discussion and feedback

ITER Organization - Scientific Internships- 2016

Safety Issues in TBM Program

Overview of Progress on the European DEMO Remote Maintenance Strategy

Vacuum Vessel In-Service Inspection_Phase 2 (WP3+WP6): Summary of Technical Specifications

Design and Development of Lower Divertor for JT-60SA

H&CD Systems and their Impact on Scenario/Economics (Lessons learned from ITER Design)

Decommissioning and Remediation after a Nuclear Accident, 3 Case Studies

ITER Research Needs. Report by David Campbell Plasma Operation Directorate

2.15 Tokamak Seismic Analysis

Measurement Probe Brochures

The Tokamak Concept. Magnetic confinement. The Tokamak concept

Safety and Environment Studies for a European DEMO Power Plant. Neill Taylor, SAE Project Leader

Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants

3 JET Operations 3.1 INTRODUCTION 3.2 EP2 SHUTDOWN

HCCB Engineering, Fabrication and Procurement, Ancillary Equipment, Interface and System Integration

The Heat Rejection System of the ITER Reactor

KSTAR Assembly and Vacuum Commissioning for the 1 st Plasma

Operation of the helium cooled DEMO fusion power plant and related safety aspects

ITER ITA NEWSLETTER NO. 22, MAY 2005 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN

Plasma Scenarios and Control

Concept of power core components of the SlimCS fusion DEMO reactor

Primary Containment Vessel Internal Investigation, Sampling and Analysis

DEMO Concept Development and Assessment of Relevant Technologies

Long term renovation inside KSTAR vacuum vessel toward steady state operation

ITER Fuelling and Glow Discharge Cleaning System Overview

Operation of the Levitated Dipole Experiment Floating Coil

Status of Design and R&D Activities for ITER Thermal Shield

MOCK-UP FACILITY FOR AHWR FUEL PIN FABRICATION: A STEP TOWARDS FULLY AUTOMATED FUEL FABRICATION

NOT EVERY HYBRID BECOMES A PRIUS: THE CASE AGAINST THE FUSION-FISSION HYBRID CONCEPT

Computational Fluid Dynamics Analysis for loads definition during accidental scenarios

exceptional Deep Sea

Design Characteristics of the Cold Neutron Source in HANARO Process System and Architecture Design

Scientific Status of ITER

Summary of Task B Activities*

Generic description of MITICA Beam Line Components and expected procurement activities

Development of a Trans-World Reactor Vessel Examination System

AMOLED DISPLAY PROTOTYPING SYSTEM CLUSTER TYPE FMM TECHNOLOGY

VV procurement by the EU

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

2008 JINST 3 S The interface to the LHC machine. Chapter Beampipe Layout

CEILING MOUNTED ARTICULATING JIB CRANE

NUCLEAR Isolation, Transfer, and Containment Solutions

CHAPTER 4. Design of Innovative Creep Testing Facility under Flowing. Sodium

A Pilot Plant as the Next Step toward an MFE Demo, )

Session 5 Shutdown schedule 2008/9 and Future shutdowns

Transcription:

ITER Remote Handling: Overview and Technical Requirements TESINI Alessandro Remote Handling Section, ITER 22 Sep 2009 Alessandro.TESINI@iter.org Page 1

Outlines ITER Remote Handling Strategy ITER RH Operation Scenario Blanket RH (PBS 23-1) Divertor RH (PBS 23-2) Transfer Cask and Port Plug (PBS 23-3) In-Vessel Viewing System (PBS 23-4) Neutral Beam System RH (PBS 23-5) Hot Cell RH (PBS 23-6) RH Test Facility (PBS 23-9) Multi-Purpose Deployer (DCR-130) Page 2

ITER Remote Handling Strategy Page 3

ITER Remote Handling Tokamak PBS-23-1 Blanket RH PBS 23-2 Divertor RH PBS 23-4 IVVS Page 4

ITER Remote Handling PBS 23-5 NB RH PBS 23-6 Hot Cell RH Tokamak building Hot Cell building PBS 23-3 Transfer cask Page 5

ITER Remote Handling Hot Cell Facility 1a) Move TCS from lift to port plug 1b) Install or removal of Tokamak component 1 1c) Move back to lift 2) Lift up or down Lift Transfer cask 2 3) Move from lift to HCF port Tokamak building 3 Page 6

RH Classifications Class 1 Class 2 Class 3 Unclass ified Those components that require scheduled remote maintenance or replacement several times during the life of the machine. Those components that do not require scheduled remote maintenance but are likely to require unscheduled and very infrequent remote maintenance. Those components not expected to require remote maintenance during the life time of ITER, but whose failure would prevent ITER operation. Those components that do not require remote maintenance either because: a)they are in a low or zero contamination / activation area and can be maintained hands-on. or b)their failure would not prevent ITER operation From ITER_D_27ZRW8 - Draft of Project Requirements (2008 Edition) For more detail classification procedure, see ITER_D_2FMAJY - ITER Remote Maintenance Management System (IRMMS) Page 7

ITER RH Operation Scenario Page 8

Machine Operation Scenario Complete Tokamak Core Construction First Plasma ITER EXPERIMENTAL SCHEDULE: ALTERNATE Hydrogen Helium Phase Complete Deuterium Phase Complete Cn: Construction phase n ICn: Integrated commissioning phase n Mn: Maintenance phase n ITER Commissioning and Operations 2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 2027 2028 2029 2030 Start Torus Pump Down Pump Down & Integrated Commissioning First Plasma End of Magnet Commissioning Blankets Divertor Plasma Restart Phase 2 Machine Assembly Commission, Cool & Vacuum Plasma Development and H&CD Commissioning All TBMs installed Phase 3 Machine Assembly / Regulatory Shutdown Full H&CD, TBM & Diagnostics Commissioning Full Heating Power @ Short Pulse N Licensing validation He H-Mode Studies Nuclear License Pre-Nuclear Shutdown & Divertor Change 100% T-fuelling capability D Plasmas on W Divertor D H-Mode Studies Trace-T Studies Shutdown 100% Tritium throughput capability Q=10 Q=10 Long Pulse C1 IC1 C2 IC2 O2 C3 O3 M1 O4 M2 O5 M3 Page 9

RH Operation (Planned shutdown) M4(8m) O6(16m) M3 (8m) O5 (16m) M2 (8m) O4 (16m) M1 (8m) O3 (20m) C3 (6m) O2 (12m) IC2 (6m) C2 (16m) IC1 (12m) C1 Maintenance Operation Maintenance DT phase Shutdown D phase Divertor change HH phase Phase 3 M/C assembly Plasma development Plasma restart IVCs install First plasma End at May 2018 RH class Freq. of Operation Activity Requirements RH equipment usage V* PBS 23-1: IVT (Blanket RH) PBS 23-2: CMM/CTM (Divertor RH) ** PBS 23-3: Transfer cask / plug RH PBS 23-4: IVVS (Viewing system) PBS 23-5: Neutral Beam RH PBS 23-6: Hot Cell RH PBS 23-X: MPD (Non-baseline RH) * Blanket exchange schedule is subject to project decision. ** Divertor exchange: two more times after DT phase. * GREEN operation period, GREY maintenance period. * After DT operation, 16 months of plasma operation, and 8 months of LTM Page 10

Blanket RH Equipment (PBS 23-1) Page 11

Blanket RH Equipment System Functions Blanket module and/or First Wall removal from and replacement to the VV wall Blanket module and/or First Wall transportation into and out of the VV Bolting for fixing modules by flexible supports Cooling pipe connection cutting, welding and weld inspection Blanket module earthing device disconnection and re-connection Insertion of NB duct liner maintenance tools Requirements and Environmental Conditions Maintenance: Replacement of all modules < 2 years. Replacement of one module < 8 weeks. Load condition: Blanket : 440 Modules of 30 types, Max. Module weight: 4.5 t Atmosphere: dry air Pressure: ~ 1 bar Temperature: < 50 C Humidity: ~ 0 % Gamma radiation dose rates: (10 6 seconds after plasma operations) In-Vessel: Max 500 Gy/hr Inside the remote handling port: tbd Gy/hr Module contact: ~75 Sv/hr Between the port plug flange (in place) and the cryostat: <100µSv/hr Contamination: tritium, activated dust (C, Be and W) Magnetic field: < 1mT From ITER_D_2FMAJY - ITER Remote Maintenance Management System (IRMMS) Page 12

Blanket RH Equipment Vehicle manipulator Module/tool transporter Articulated rail Rail support equipment Cable handling equipment Page 13

Rail Deploying and Rail Support Equipment Vehicle Manipulator Rail Cable Handling Equipment Transfer mover Rail Support Equipment Transfer frame for Cable Handling Equipment Sliding Beam Page 14

Rail Support Equipment and Module Transporter Vehicle Manipulator Rail Support Equipment Tractor Cable Handling Equipment Transfer frame for Cable Handling Equipment Rail Module / Tool transporter Page 15

The Rail Deployment System Configuration Blanket model Vacuum vessel Rail Intermediate cask Rail Rail connecting equipment Sliding Beam Rail Storage Table IVT cask CBP Vehicle/ manipulator Vehicle fixing arm Rail positioning arm Tractor Page 16

Rail Deployment Sequence Rail Vehicle 1 2 1) Positioning vehicle inside VV by vehicle fixing arm 2) Deploying rail by vehicle traveling axis Vehicle fixing arm Rail positioning arm Rail positioning arm 3 Rail positioning arm 4 Final rail joint 3) Arcing rail by rail positioning arm 4) Deploying final rail join Rail support Cable handling 5 6 Vehicle fixing arm 5) Installing rail support equipment and cable handling equipment 6) Removing vehicle fixing arm Page 17

Prototype Page 18

Divertor RH Equipment (PBS 23-2) Page 19

Divertor RH Equipment System Functions Insertion / extraction of divertor cassettes and their transport to/from a transfer cask docked at divertor level RH ports Insertion / extraction of divertor level diagnostic assemblies and their transport to/from a transfer cask docked at divertor level RH ports Removal / replacement of the divertor level RH port primary closure plate (PCP) Dust removal in and around the divertor region during the cassette removal process Cutting, welding, alignment and inspection of cassette cooling pipes, and gas injection lines. Requirements and Environmental Conditions Maintenance: Replacement of the entire divertor < 6 months Replacement of one cassette < 8 weeks (varies depending on location of faulty cassette). Load condition: Standard cassette handling: ~ 9 t Central (or diagnostic) cassette handling: ~ 11t Atmosphere: dry air Pressure: ~ 1 bar Temperature: < 50 C Gamma radiation dose rates: (10 6 seconds after plasma operations) In-Vessel: 100 Gy/hr in divertor region. Cassette contact: ~ 75 Gy/h (TBC) Inside the remote handling port: tbd Gy/hr Between the port plug flange (in place) and the cryostat: <100µSv/hr Contamination: tritium, activated dust (C, Be and W) Magnetic field: < 1mT From ITER_D_2FMAJY - ITER Remote Maintenance Management System (IRMMS) Page 20

Divertor RH Equipment Diagnostic Port 10 RH Port 8 Cryopump Port 12 Cryopump Port 6 RH Port 14 Cryopump Port 4 Diagnostic Port 16 RH Port 2 Cryopump Port 18 Page 21

Divertor RH Equipment CMM CTM Transfer Cask Cassette Multifunctional Mover (CMM) Cassette Toroidal Mover (CTM) Page 22

Standard Cassette Installation Sequence 1 2 1) Connect the cask to the port plug with a standard divertor cassette 2) CMM carries the cassette inside the VV 3) Connect the cassette to CTM 4) CTM moves the cassette toroidally 3 4 5) Positioning the cassette 6) Weld the pipes by using CTM MAM 5 6 Page 23

Prototype Dummy cassette Divertor Test Platform 2. Tampere, Finland CMM Prototype Page 24

Transfer Cask and Port Plug RH Equipment (PBS 23-3) Page 25

Transfer Cask System & Port Plug RH System Functions The Cask and Plug Remote Handling Systems shall provide the means for the remote transfer of (clean/activated/contaminated) in-vessel components and Remote Handling Equipment between Hot Cell Facility and Vacuum Vessel through dedicated galleries and lift in the ITER buildings. shall also provide means for transfer during Remote Handling Equipment rescue operations. shall also provide means for transfer during in Vessel initial assembly and testing operations. Preparatory activities, prior to initial cask docking, shall involve hands-on operations, including bio-shield plug removal, clearance of pipes, cables and other plug services, and cutting of the vacuum seal. Requirements and Environmental Conditions Transfer Cask (inside) Load condition: Upper port plug: 25t, Equatorial port plug: 45t Dry air Pressure: ~ 1 bar (min 0.95 bar - max 1.05 bar) Temperature: < 50 C (tbd) Gamma radiation dose rates: 120Gy/hr with 2 blanket modules, 50Gy/hr with diverter cassette. Contamination: tritium, activated dust (C, Be and W) Magnetic field: <1mT From ITER_D_2DTP9H - SRD-23-03 (Casks and Plug Handling Systems) Page 26

Transfer Cask System Envenlope - About 50 t empty - Size: 3.7m x 2.7m x 8.5m, - Confine tritium, no shielding. Pallet ~ 100 persons city bus In-Cask Equipments ATS Page 27

Port Plugs & In-Cask Equipment (1) Components to be transferred Plugs - Diagnostic Plugs (PBS 55) - Electron Cyclotron Heating (ECH) Plugs (PBS 52) - Ion Cyclotron Heating (ICH) Plugs (PBS 51) - Lower Hybrid Heating (LHH) Plugs (PBS 54) - Test Blanket Module (TBM) Plugs (PBS 56) NB cell upper port diagnostic tubes (PBS 55) Blanket RH Equipment (PBS 23 01) (& 2 Blanket Modules) Divertor RH Equipment (PBS 23 02) (& 1DIV K7) In-Vessel Viewing System Plugs(PBS 23 04) Torus cryopumps (PBS 31) 21 dedicated transfer casks with 7 different types ( ) Page 28

Port Plugs & In-Cask Equipment (2) NB Cell Upper Plug Diag. central tube Upper Plug Eq. Plug Divertor Page 29

Docking Port for Each Cask VV Upper TCS for Plugs Upper rescue TCS All level rescue Up Tractor RESCUE RESCUE VEHICLE NBCELL TCS NB CELL EQ TCS for Plugs Eq Tractor? EQ TCS for Blanket Modules IVT IVT EQ rescue TCS RESCUE LIFT HOT CELL Divertor TCS for K7 CTM CMM IVVS TCS IVVS? Cryopump TCS? Lower rescue TCS RESCUE Page 30

Docking Transfer Cask System to a Port Port 1) Entering into a port for maintenance operation. 2) Approaching to the port. TCS 1 2 Pallet Cask ATS Positioning sensor Actuation 3 4 3) Supporting by the pallet system, and removing the ATS outside of the port. 4) Positioning of the cask for connection to the port. 5) Connection to the port. 6) Opening the double seal door. 5 Double seal door 6 Page 31

In-Vessel Viewing System (PBS 23-4) Page 32

In-Vessel Viewing System (IVVS) System Functions shall allow for in-vessel inspection of plasma-facing surfaces to look for possible damage caused during plasma operations. shall also be used for metrology measurements of the plasma chamber and its components. Requirements and Environmental Conditions Maintenance: Visual Inspection of one ITER sector: < 2 hrs Dimensional survey of one ITER sector: < 8 hrs Performance: shall provide viewing images with a spatial resolution better than 1mm at target distances of 0.5m-4m and better than 3mm at target distances up to 10m. shall be capable of providing metrology at key points of the divertor and first wall regions with a reference accuracy of better than ±0.5mm at 5m target distance. Atmosphere: Vacuum @ 10-3 Pa Temperature: 120 C (240 C for baking) Gamma radiation dose rates: 5000 Gy/hr. Total dose 10 MGy. Magnetic field: < 1 milli Tesla From ITER_D_2FMAJY - ITER Remote Maintenance Management System (IRMMS) ITER_D_29NC9X - SRD-23-04 (In-Vessel Viewing System) from DOORS Page 33

In-Vessel Viewing System (IVVS) IVVS Port IVVS Port Cryo pump port Triangula r support IVVS Divertor Six installation port: #03, 05, 09, 11, 15, 17 Page 34

Coverage of IVVS Inspection In board position Mid position Out board position Coverage of whole VV surface Probe Position Out board Mid In board Coverage Incident angle of 60deg (70deg) 54.82% (73.91%) 56.29% (70.84%) 56.29% (70.15%) Coverage of divertor area Page 35

Prototype viewing PoP IVVS (ENEA) metrology Typical spherical image obtained by IVVS probe - Metrology results at 3.75m and 0 deg - Scanning time: 60 minutes - Resolution < 1mm until 70 deg incident angle 1 0 3 mm 10 mm Page 36

Neutral Beam System RH Equipment (PBS 23-5) Page 37

Neutral Beam System RH Equipment System Functions Removal and replacement of the caesium oven fuelling system Removal and replacement of the beam source Removal and replacement of the beam line components Removal and replacement of the NB gate valve and duct bellows (tbc) Requirements and Environmental Conditions Maintenance: Time required for removal and replacement of the caesium oven fuelling system 7 days That of beam source, the beam line components, the NB gate valve and duct bellows - tbd Load condition: NB Injector assembly weight: 26 t Passive Magnetic Shield large end plate weight: 6 t Beam Source Vessel end plate weight: 7.5 t Atmosphere: Air Pressure: ~ 1 bar Temperature: Ambient Gamma radiation dose rates: Around ion source: < 0.4 mgy/hr Outside the ion source vacuum boundary: < 0.01Gy/hr Outside the beam line: < 0.01 Gy/hr Outside the magnetic shield: < 10-4 Gy/hr Around the fast shutter:< 0.1 Gy/hr Contamination: tritium, activated dust (C, Be and W) Magnetic field: ~ 0.1 Tesla From ITER_D_2FMAJY - ITER Remote Maintenance Management System (IRMMS) Page 38

Neutral Beam System (3) Duct liner maintenance Duct liner (2) Beam line components maintenance Beam source Calorimeter Residual ion dump Neutraliser (1) Beam source maintenance Page 39

Deployment of RH system Monorail crane HNB #3 DNB HNB #1 HNB #2 Page 40

Beam Source RH (1) Manipulator 1 2 1) Exchange the caesium oven (RH Class 1) Caesium oven Manipulator transporter NB cell crane 3 4 Manipulator 2) Opening the BSV end plate 3) Disconnection of beam source service 4) Removing the beam source Beam source trolley Page 41

Beam Line Components RH (2) 1 2 1) Opening the BLV lid 2) Moving the manipulator 3) Maintaining the beam line components 3 Page 42

Duct Liner RH (3) RH Port IVT support Duct Liner Module IVT IVT end effectpr 1 2 1) Move duct liner into VV from transfer cask 2) Transfer the DLM from the RH port to the NB Port in inside of VV by using IVT 3) Positioning the DLM and inserting it to the NB port. 4) Service connection for the DLM Duct Liner Module DLM Transporter 3 4 Page 43

Hot Cell RH Equipment (PBS 23-6) Page 44

Hot Cell RH Equipment System Functions Transfer of component within, in an out of the Hot Cell, Storage of machine components and RH equipment. Cleaning and dust removal. Repair or refurbishment operations, including removal/installation of parts, minor machining operations, welding. Inspection of components (such as Visual/Ultrasonic/leak testing). Maintenance of the Hot Cell infrastructure and equipment located in the red zones (including RH equipment). Remote maintenance inside the Hot Cell building for the following ITER components: Divertor Cassettes system. Blanket modules system. Vacuum vessel port plugs and diagnostic systems. Neutral beam cell upper port diagnostic tubes. In-Vessel and HC RH equipment. In-Vessel Viewing System. Torus Cryopumps. Requirements and Environmental Conditions The pressure is 1 bar absolute Maximum environmental temperature of 35 C The relative humidity is 25 % Max No magnetic field The contamination comprise mainly tritium, but possibly also activated dust (C, Be and W) Typical maximum environmental radiation dose rate of 460 Gy/hour (possible changes as ITER design progresses). From ITER_D_27YUC4 - SRD-23-06 (Hot Cell Remote Handling Equipment) Page 45

Hot Cell Layout Page 46

Hot Cell RH Equipment The HC RH system shall comprise the following equipment: Boom-style RH transporter(s) Jib cranes transporters Lifting jigs Dexterous telemanipulator(s) end effectors Direct viewing telemanipulators Inspection equipment (including weld NDT, visual inspection, metrology) Cleaning equipment (Vacuum cleaner). Plug refurbishment &test Plug storage Divertor refurbishment & test Divertor storage Transfer cask Layout can be changed Page 47

Hot Cell RH for Divertor Cassette DIVERTOR CASSETTES REFURBISHMENT : on-line for 54 divertor cassettes, all available requirements at the time have been taken into account Divertor cassette testing & tools support Page 48

Hot Cell RH for Port Plugs and TBM PLUGS REFURBISHMENT : some requirements available at the time have been taken into account Limited provision for plug testing T B M REFURBISHMENT: 1. TBM plug fully inserted into Hot Cell 2. Spare TBM plugs Page 49

RH Test Facility (PBS-23-9) Page 50

RHTF Requirements Test Facilities Required for all ( IRMS) elements: (ITER Remote Maintenance System) In-Vessel Transporter (IVT), transfer casks, end effectors & tooling Cassette Multi-Function Mover (CMM), casks, end effectors & tooling Cassette Toriodal Mover (CTM), umbilical & tooling In-Vessel Viewing System (IVVS) transfer cask based Cryopump system transfer cask based Upper plug system transfer cask based Equatorial plug system transfer cask based NB Duct Liner transfer cask, transporters, manipulators & tooling Hot Cell systems transporters, manipulators & tooling NB Cell systems transporters, manipulators & tooling Multi-purpose Deployer (MPD), transfer casks, end effectors & tooling* ELM Coils transfer cask, transporters, manipulators & tooling* * TBC Page 51

RHTF Functions IRMS Requirements (2) Page 52

Hot RHTF & Cold RHTF HOT RHTF host by HC building Cold RHTF host by Assembly Hall building Page 53

Example of RHTF Page 54

Multi-Purpose Deployer (DCR-130 accepted) Page 55

In-Vessel Requirements (Non-baseline in RH) Mandatory Defined at a certain extent Definition on going Requirement Dust accumulation monitoring and removal Tritium inventory monitoring Vacuum vessel inspection Vacuum vessel leak identification In-Vessel diagnostics maintenance VS and ELMs coils Maintenance NB Duct Liner Tile replacement Rescue operation of the other RH systems Activity Dust sampling Dust removal Tritium sampling Tritium removal Periodic inspection Periodic requalification Leak localisation Calibration, alignment, inspection, replacement, cleaning Maintenance Assistance Rescue operation Expected Frequency of Operation 16 months* 16 months* 16 months* Main system is baking every 40 months every 10 years Expected few times in ITER operation 16 months Based on hypotheses of dust (and tritium) inventory growing-up, to be validated through R&D on going and H, D phase. Safety Authority will ask to do that at any shutdown for ALARA principle TBD TBD RH class 1 1 1 2 1 1 1 TBD TBD TBD Page 56

MPD System MPD Transporter Transfer Cask System VV MPD Manipulator Task Module Page 57

MPD Requirements MPD Transporter Installation: Deployment from a standard and an intermediate transfer cask through 4 designated IVT entry ports (N 3,8,12 & 17). Shall be deployed without IVT because of space limitation. Load capability: Deployment of end effectors with 100kg self weight plus a 250kg payload within the access zone. Deployment of bilateral manipulator arms with a 100kg payload within the access zone. Additional payload capacity of 2 tonnes for all accessible position in VV. Kinematic performance: Reach over a segment of VV of ±50. Maximum Point of Reference (PoR) speed of 100 mm/s. PoR positional accuracy of ±10mm. Others: Possibility to recover the MPD following a single point failure No hydraulic power to be used MPD Manipulator Force reflecting servo-manipulation Bilateral configuration Long-term load capacity in three DoF of 30kg per arm No hydraulic power to be used Page 58

MPD Requirements MPD Task Module Provides constant availability of tools (and/or components) anywhere within VV. Contains following tools: Page 59

MPD Requirements MPD Transfer Cask Standard Transfer Cask MPD main cask based on an Standard Equatorial Cask Same pallet, same ATS, same enclosures, cooling system and DSD. A specific in-cask handling equipment Carriage for the transporter with 2 rails on the cask s base plate Designed for a maximum payload of 45 T Intermediate Cask MPD intermediate cask based on the IVT intermediate cask concept Same shorter pallet, same shorter ATS, same enclosures, cooling system and DSD. A specific in-cask equipments (OTL data) For tools (gas blower, He sniffer, He spray, TIG weld and calibration source), For camera inspection tool (radiation hardened), For umbilical (electrical, pipe and special cable) Docking at the rear side of the standard TC. Recovery Cask MPD recovery cask based on the MPD transporter cask To mate with the transporter cask after removing the intermediate cask A specific in-cask handling equipment which can grip the transporter to pull it back into the cask Page 60

Deployment of MPD Transporter 1 2 1) MPD stowed inside transfer cask Transporter End effector Cask 3 4 2) Passage through the port 3) Rotate axis 4 to deploy inside VV 4) Rotate axis 8 to deploy inside VV 5 6 5) Unfold the arm 6) Full extension of the arm: access to 50 sector Deployment Video Page 61

M TM M MPD Operation Concept - Collaborative working Operation of the MPD will require a number of tools which must be made available ideally at the manipulator work site for operation time efficiency. For this reason a second MPD is deployed with the concept Task Module mounted upon it. Work space coverage Task module Manipulator Primary MPD system M TM Secondary MPD system TM M TM Collaboration Video Page 62

Conclusion Remote Handling (RH) of the tokamak components is an essential part of the overall ITER experiment, and relies on the close interaction between the ITER Remote maintenance System (IRMS) and the ITER components. ITER Remote Handling is composed of as follows: Blanket RH (PBS 23-1) Divertor RH (PBS 23-2) Transfer Cask and Port Plug (PBS 23-3) In-Vessel Viewing System (PBS 23-4) Neutral Beam System RH (PBS 23-5) Hot Cell RH (PBS 23-6) RH Test Facility (PBS 23-9) Multi-Purpose Deployer (DCR-130) Page 63