# Presentation: 472178

## W.R.Spears
for the ITER International and Participant Teams

Forum on the Future of Fusion
Washington, 19-21st November, 2003

**for the ITER International and Participant Teams**
**Forum on the Future of Fusion**
**Washington, 19-21st November, 2003**

**Status of ITER**

## Content

**Technical Status and Developments**
**Preparations for Construction**
**Cultural Improvements**
**New Tools**
**Negotiations Status**
**Site Choice**
**Joint Implementation**
**Perspective for 2004**
**Timescale for Parties**
**Activities for Project**

## What is ITER?

**Programmatic**
**Show scientific and technological feasibility of fusion energy for peaceful purposes.**
**Technical**
**High plasma fusion power gain (Q = 10), extended DT burn - steady state ultimate goal.**
**Test essential technologies in reactor-relevant physics and technology environment.**
**Test high-heat-flux and nuclear components -  average neutron wall load ≥ 0.5 MW/m****2**** and average lifetime neutron fluence of ≥ 0.3 MWa/m****2****.**
**Demonstrate safety and environmental acceptability of fusion.**
**Strategic**
**Answer, in single device, all feasibility issues needed to define a subsequent electricity-generating fusion power plant - except for material developments to provide low activation and larger 14 MeV neutron resistance for in-vessel components **

_**                 **_

## ITER Inductive Performance

**For the first time in the history of the development of magnetic confinement fusion as an energy source, Q >> 1.  **
**The plasma will be dominated by self-heating from alpha particles generated in the reaction of deuterium and tritium fuel.**
**Reference scenario (ELMy H-mode) with inboard fuelling and high triangularity would provide Q>10 even at today’s most severe experimental density limits.**

**(Operation range shown for various helium confinement assumptions)**

## ITER Hybrid and Steady State Performance

**Performance projections for hybrid operation, stretching the burn time up to steady state, are for limits (e.g. in plasma density) seen in many of today’s experiments. **
**Some experiments show that if the power entering the plasma core is sufficiently high, a second transport barrier occurs inside, limiting even more the heat conduction across the plasma.  **
**Control of this barrier would significantly increase Q for a given burn time.**

**Typical inductively driven burn time of ITER ~ 7 minutes.**
**Longer burn desirable to test steam-raising tritium-breeding test blankets, - more typical of power reactor conditions. **

## Design - Main Features

**Design - Main Features**

**Divertor**
**54 cassettes**

**Central Solenoid**
**Nb****3****Sn, 6 modules**

**Outer Intercoil Structure**

**Toroidal Field Coil**
**Nb****3****Sn, 18, wedged**

**Poloidal Field Coil**
**Nb-Ti, 6**

**Machine Gravity Supports**
**(recently remodelled)**

**Blanket Module**
**421 modules**

**Vacuum Vessel**
**9 sectors**

**Cryostat**
**24 m high x 28 m dia.**

**Port Plug (IC Heating)**
**6 heating**
**3 test blankets**
**2 limiters/RH**
**rem. diagnostics**

**Torus Cryopump**
**8, rearranged**

## Main changes in ITER since July 2001

**Magnets**
**increased critical current (from ~6 to ~800 A/mm****2****)**
**use of stainless steel jacketing in all conductors**
**outer intercoil structure uses friction joint of welded plates**
**Vessel/Blanket**
**support arrangement simplified **
**nine lower ports **
**blanket module has FW supported from welded central leg**
**improved interlocking of thermal shield **
**Building/Services**
**introduction of port cells**
**relocate gallery equipment - access, e/m loads**
**incorporate seismic isolation for Cadarache/Rokkasho**
**improve site layout**

## Change Control

**Technical Coordination Meetings (TCM)**
**Chaired by Interim Project Leader (IPL)**
**Decides on change proposals (DCRs)**
**Organises and schedules supporting work and priorities**
**Design Change Requests (DCR)**
**Document proposals for changes**
**Design Work Orders (DWO)**
**Request CAD effort**
**Design Work Check (DWC)**
**Process to check drawing ofice output**
**Design Integration/Drawing Office (DIDO) Meetings**
**Reviews ongoing CAD progress, prioritises new CAD effort allocation, and schedules detailed design reviews**

## ITER Transitional Arrangements

**Due to positive direction of Negotiations, ITER Transitional Arrangements (ITA) began in January 2002 and will continue until the IIFEO is established.**
**Enable IIFEO to function without delay following signature/ratification of the Agreement.**
**establish interim key organisational elements: Interim Project Team and Leader, Preparatory Committee of ITER Council;**
**following site choice, establish provisionally staffed interim joint work site there;**
**coordinate Parties’ domestic preparations for contributing to ITER Joint Implementation;**
**identify and provisionally assign potential senior staff;**
**elaborate administrative procedures, documents and other tools foreseen for managing ITER Joint Implementation.**
**continue joint technical preparations.**

## Technical Preparations

**Licensing application - close dialogue with potential regulators ******** review design to ensure its quality and completeness and carry out additional safety analyses.**
**Establish technical specifications for long-lead items, i.e. mainly magnets, vacuum vessel, and buildings.**
**Enhance technical organisation to maintain ITER design and prepare for an efficient start of construction, and provide reliable basis for licensing, including **
**Upgrading of CAD system**
**Introduction of virtual product data management system (VPDM)**
**Introduce new document management system (DMS)**
**Preparation for later introduction of asset tracking system (ATS)**
**Improvement of underlying structures and systems  (mainly IT)**
**Preparation for move to construction site**

## Construction Schedule

**7 year construction**
**1 year integrated commissioning**
**IIFEO established ~2 years before award of construction license**
**Long lead item calls for tender sent out and procurement started before license awarded**
**Success-oriented schedule**
**First plasma in 2014 **

## Procurement Specifications

**Drafting of detailed technical specifications for long lead items:**
**Magnets:**
**strand and conductor**
**PF and TF coils**
**Vessel:**
**main vessel and ports**
**blanket coolant manifolds**
**Buildings:**
**tokamak complex**
**cryogenic halls used for PF coil winding**
**service tunnels**
**Task Forces established with PT/IT membership to complete work in necesary detail and with industrial realism**
**Development of other procurement specifications to cover interfaces with long lead items - resource limited**

## Document and Model Management Tools

**IDoMS lacks basic commercial product features:**
**tree/network navigation of linked documents, **
**approval workflow tracking, **
**document validity (“effectivity”) according to circumstances,**
**electronic signature, **
**realistic  user roles and security.**
**	****These quality control features needed for licensing, and controlled worldwide access.**
**ITER needs “virtual product data management” (VPDM) software for 3D digital mockup, essential for configuration management in the tokamak/ pit. **
**clash detection, utility routing, and increasingly collaborative design with the Participants, need better tools to control the configuration and available space.  **
**CATIA 4 soon obsolete. CATIA 5, cannot be used without a PDM. Advantageous to upgrade:**
**nearly all procurement models are in one system;**
**to be in tune with manufacturers, who have already upgraded, and to rehearse conversion processes with other manufacturer’s CAD systems;**
**to train operators while deadlines are not so pressing.**
**to rehearse processes and tailor software systems essential post-IIFEO.**

## CATIA/VPDM/DMS implementation timescale

- 2003

- 2004

- CERN
- EDMS
- Pilot

- DMS
- VPDM
- Options
- Study

- Smarteam
- Pilot

- VPM
- Pilot

- Initial work with CATIA V5

- DMS
- Selection

- DMS fully productive

- VPDM
- Selection

- VPDM fully productive

- Expansion as needed

## Temporary Documentation

**Before introduction of new document management system  need to define design status and provide area for information exchange.**

## Negotiations

**draft Joint Implementation Agreement**
**select ITER construction site**
**agree how the procurement  and costs will be shared**
**define how the project will be managed **
**identify the Director General and senior staff**

## Potential Sites

**France**
**(Cadarache)**

**Spain**
**Vandellòs**

**Canada**
**(Clarington)**

**Japan**
**(Rokkasho)**

**Joint assessment of sites (JASS) has concluded all sites are feasible**

## Timetable for Consensus on Site Preference and the JIA for Signature

**2002**

**Site Evaluation (JASS) Process**

**Consensus on Preferred Site / Cost Sharing / DG**

**JULY**

**AUG**

**SEPT**

**OCT**

**NOV**

**N5**
**Toronto****Sept. 17/18**

**DEC**

**N6****Aomori****Oct 29/30**

**N7****Barcelona****Dec 10/11**

**JAN**

**FEB**

**2003**

**N8**
**St. Petersburg**

**Development of Scenarios**

**Clarington Evaluation**

**Higher/Political Level Discussions Leading to Site Decision**

**Meetings**

**Process**

**MAR**

**JULY**

**JUNE**

**MAY**

**APR**

**Final Joint Implementation Agreement**

**Site-Specific Negotiations**

- N9

- N10

**Final JASS Report**

***Timetable for Consensus on ******Site Preference and the JIA for Signature***

**Rokkasho Evaluation**

**Cadarache & Vandellos Evaluation**

## ITER International Fusion Energy Organisation

**           ****Services**
**                 ****Support for **
**                 •  ****Project Management**
**                 •  ****Computer Network**
**                 •  ****Technical work**
**                 •  ****Clerical work**
**                   ****etc.**

**ITER International Fusion Energy Organisation**

**IIFEO**

**Field Team**

**Field Team**

**Field Team**

**Council**

**Science and**
**Technology **
**Advisory **
**Committee**

**Construction**
**Programme**
**Advisory**
**Committee**

**Director-General**
**(DG)**

**Auditors**

**Organisation Personnel **
**(professionals + support staff)**

**Domestic**
**Agency**

**Industries and**
**Other Organisations**

**Contract**

**for construction phase**

**Host Country**

**Central Team**

**DDGs**

**Project**
**Manage.**

**Admin.**

**Integration**
**Interface**

**Procure-**
**ment**

**QA.**

**Physics**

**Safety**
**Licensing**

**Host **
**Relation**

**Staff of DG**

**Domestic**
**Agency**

**Industries and**
**Other Organisations**

**Domestic**
**Agency**

**Industries and**
**Other Organisations**

**Organisation/Host Relation**

## Financial Arrangements

**Ensures fair return**
**Ensures fair share of value to project**
**Allows Parties to get involved in what they view as key technologies**
**Project needs the power to intevene to control procurements of interfacing systems and introduce essential design changes which may affect cost**

## Cost

**Cost of ITER established using multi-party industrial estimates consolidated using uniform material costs and labour rates.**
**Cost estimate established as basis of sharing and as a valuation to give Parties indicative costs.  Actual costs depend on Parties individual procurement practices.**

- 1988

## Cost Sharing

**EU: TF(0.5), conductors, cassette and outer target, vac.pumps, div. RH, casks (0.5), isotope sep., IC, EC, diag.**
**JA: TF(0.5), conductors, inner target, blanket RH, EC, diag.**
**KO: conductors, vessel ports (0.67), blanket (0.2), assembly tools, thermal shield, T storage, AC/DC (0.65), diag.**
**CN: magnet supports, correction coils, conductors, blanket (0.2), cryostat, gas injection, casks (0.5), HV substation, AC/DC (0.35), diag.**
**RF: PF1, conductors, vessel ports (0.33), blanket (0.2), port limiters, flexibles, dome and PFC tests, Discharge circuits, EC, diag.**
**US: CS(0.5), conductors, blanket (0.1), vac.pumps, pellet inj., vessel/in-vessel cooling, tok exh. proc., IC, EC, diag.**
**Fund: Feeders, Shielding, vac.pumps, misc vac., viewing, NB RH, Hot cell eq., cryodist., diag., CODAC, other sundry items**

**EU/JA**
**Site**

**Canadian**
**Site**

**Remaining allocation depends on site**

## Risk Management

**ITER design development/detailing since July 2001 has not primarily reduced cost but reduced risk of cost overrun and created margins to cover the unforeseen.  Margins actually realised will not be seen by the project for items provided in kind.**
**Because ITER is a first-of-a-kind design, considerable R&D was done to minimise technical problems of component fabrication, and to avoid later delays, design changes, regulatory problems, and difficulties in assembly. **
**Despite this, suppliers have to demonstrate high success rate in production.  Where more than one Party is involved, staged contracts can be used, plus donation of unused funds to the project from inadequate producer’s Party, to minimise overall risks to production.**
**To cover delivery delays during construction, penalty clauses must be included in contracts to compensate the other Parties and the project.  The Project Team needs to be closely involved to help recognise and limit such occurrences.**
**Such an experiment cannot be built without some changes during construction.  The strong presence of the Project Team on the supplier’s premises should allow some difficulties to be absorbed by adapting interfaces with later manufactured items.  But in the end, the other Parties may have to jointly compensate the manufacturing Party for consequent cost increases beyond that Party’s margins.**
**What to do in each of the situations that could arise will be documented in the JIA.**

## Preparation toward ITER Organization (Draft)

- Decision Making

- Technical Work

- Legal Work

- NSSG

- N

- P

- IPC

-            IT
- (Interim Leader)

- ITER International Fusion Energy Organization

- Council

- Director General

- ITER
- Preparatory
- Committee
- (IPC)

- D-G Nominee
- and
- Transitional Team
- (Participant team)

- Working Group
- With
- Topical Sub Groups
- (with T.T.)

- Completion
- of
- Draft
- Agreement
- (Initial)

- Agreement
- Entering
- Into Force

**Preparatory**
**Tasks**

- Site, Cost &
- Senior Staff
- Decision

## Timetable for Establishing ITER 

**Domestic Checking Process**

**Consensus on Preferred Site / Cost Sharing / DG**

**NOV**

**DEC**

**JAN**

**FEB**

**MAR**

**APR**

**MAY**

**JUN**

**2004**

**JA**

**Negotiators Initialing **
**of Agreement**

**JUL**

**NOV**

**OCT**

**SEP**

**AUG**

**Establishment of the IIFEO**

***Timetable for Establishing ITER ***
***International Fusion Energy Organisation***

**Approval by Diet**

**Sign and submit to Diet**

**CA**

**Create Domestic Agency**

**Cabinet Approval**

**CN**

**Signature**

**EU**

**Signature**

**Ratification**

**Approval by National Assy.**

**Sign and submit to NA**

**KO**

**RF**

**US**

**Signature**

**Consultation with Senate**

**Signature**

**Council Procedure**

**Finalise/Verify JIA**

## Computer Infrastructure Implementation

- 2004

- 2005

- DMS fully productive

- VPDM fully productive

- CATIA 5 Expansion

- DMS Server Basic Configuration

- VPDM Server Basic Configuration

- Establish Local Mirror

- Remaining Servers Basic Configuration

- Establish ITER Site Mirror

- Transfer Servers to ITER site

## Conclusions

**The ITER Transitional Arrangements are being used by the project to get many things ready that will ease the path once the negotiations are successfully completed:**
**finalisation of long lead time procurement packages**
**preparation of safety case for licensing bodies**
**adoption of tools that are necessary for project and quality control**
**•****	****The inter-governmental negotiations aiming at an agreement on construction and operation of ITER are nearing completion and, if all goes well, can be expected to lead to the start of the establishment of the construction team in 2004.**
**	****	****	****	****	****     **** *********

## ITER Nominal Parameters

**Total fusion power****	****	****	****	****	****500 MW (700MW)**
**Q = fusion power/auxiliary heating power****	****	****≥10 (inductive)**
**Average neutron wall loading ****	****	****	****0.57 MW/m****2**** (0.8 MW/m****2****)**
**Plasma inductive burn time****	****	****	****	****≥ 300 s **
**Plasma major radius ****	****	****	****	****6.2 m**
**Plasma minor radius****	****	****	****	****2.0 m**
**Plasma current (inductive, I****p****)****	****	****	****15 MA (17.4 MA)**
**Vertical elongation @95% flux surface/separatrix****	****1.70/1.85**
**Triangularity @95% flux surface/separatrix****	****	****0.33/0.49**
**Safety factor @95% flux surface****	****	****	****3.0**
**Toroidal field @ 6.2 m radius****	****	****	****5.3 T**
**Plasma volume****	****	****	****	****	****837 m****3**
**Plasma surface****	****	****	****	****	****678 m****2**
**Installed auxiliary heating/current drive power****	****	****73 MW (100 MW)****	**

## Work on Outer Intercoil Structure

**These function as both shear panels, to provide out-of-plane support, and to hold in the TF coils. They have insulating joints which must transmit tension and shear. **
**Two concepts (box and friction), two fabrication methods (casting of thick sections and welding of plates). **
**Stress analysis - problems with box design due to fatigue in the bolts, and opening of flanges connecting adjacent boxes which overloads the shear keys. **
**Friction joint design selected, which leads to the selection of the welded plate route.**

## Vacuum Vessel Support System

**VV supported independently of magnets at the lower ports**
**Possible to adjust the VV in the pit after welding of the sectors.**
**Snubbers used to limit the radial movement during earthquake**
**Locate parts requiring maintenance outside cryostat **
**Vertical ropes for upwards loads**

**Vacuum Vessel Support System**

## VV Lower ports

- .

**9 large VV penetrations at divertor level**
**3 ports for divertor cassette maintenance **
**2 for diagnostic equipment**
**4 ducts (connected to 8 torus pumps)**
**Cryostat cryopumps can be made similar to the torus pumps and can be located at the same level with improved maintainability**

**VV Lower ports**

## Thermal Shield

**Thermal Shield**

**Cryostat thermal shield close to the magnet structures and supported in the central region by the TF coils**
**Most labyrinths eliminated**
**Reduced thermal radiation to 4K structures**
**Separation of cold volume from the part crossed by water pipes **
**Reduced total surface (and cost) of the TS.**

## Port Cell Layout

**Second containment barrier moved to port cell door**
**Reduced number of operations in irradiated areas.**

## Design - Magnets and Structures

**Superconducting. **
**Nb****3****Sn toroidal field (TF) coils produce confining/stabilizing toroidal field; **
**NbTi poloidal field (PF) coils position and shape plasma; **
**modular Nb****3****Sn central solenoid (CS) coil induces current in the plasma.**
**correction coils correct error fields due to manufacturing/assembly imperfections, and stabilize plasma against resistive wall modes.**
**TF coil case provides main structure of the magnet system and the machine core. PF coils and vacuum vessel are linked to it.  All interaction forces resisted internally.  **
**TF coil inboard legs wedged together along their side walls and linked at top and bottom by two strong coaxial rings which provide toroidal compression and resist the local de-wedging of those legs under load. **
**On the outboard leg, out-of-plane support provided by intercoil structures integrated with TF coil cases. **
**Magnet system weighs ~ 8,700 t.**

## Design - Main Vacuum Vessel

**Primary function**
**high quality vacuum for the plasma**
**first confinement barrier to radioactive materials**
**second barrier for the separation of air from potential sources of in-vessel hydrogen generation.**
**Decay heat of all in-vessel components can be removed by the water in the VV primary heat transfer system (PHTS) system, even in conditions when the other PHTSs are not functioning. **
**9 x 40° vessel sectors****.**

## Design - Blanket

**421 blanket modules with detachable faceted first wall (FW) with Be armour on a water-cooled copper substrate, attached to a SS shielding block - minimises radioactive waste and simplifies manufacture. **
**Blanket cooling channels are mounted on the vessel. **
**Design strongly affected by need to resist electromagnetic forces.**
**Initial blanket acts solely as a neutron shield, and tritium breeding experiments are carried out on test blanket modules inserted and withdrawn at radial equatorial ports.  **
**The outboard blanket may later be replaced by a tritium breeding blanket. **

- Inlet/outlet manifolds

- First wall panel

- Hole to fit
- flexible support

- Flexible supports

- Vessel

- Shield block

- Shear key

- Gripping hole

- Electrical strap

## Design - Vessel & In-Vessel

**Double-walled vacuum vessel lined by modular removable components, including blanket modules, divertor cassettes, and diagnostics sensors, as well as port plugs for limiters, heating antennae, diagnostics and test blanket modules.  All these removable components are mechanically attached to the VV.  The total vessel/in-vessel mass is ~10,000 t.**
**Components absorb most of the radiated heat from the plasma and protect the magnet coils from excessive nuclear radiation. Shielding is steel and water. A tight fitting configuration of the VV to the plasma aids passive plasma vertical stability, and ferromagnetic material “inserts” in the VV located in the shadow of the TF coils reduce toroidal field ripple and its associated particle losses. **

## Design - Divertor

**54 cassettes. **
**Target and divertor floor form a V which traps neutral particles, protecting the target plates, without adversely affecting helium removal.**
**Large openings between the inner and outer divertor balance heat loads in the inboard and outboard channels. **
**Design uses C at the vertical target strike points.  W is the backup. C is best able to withstand large power density pulses (ELMs, disruptions), but produces tritiated dust and T co-deposited with C which has to be periodically removed. The choice can be made at the time of procurement. **

- Vertical target (W part)

- Dome (W)

- Vertical target (C part)

- Transparent liner for pumping

## Design - Heating/Current Drive

**Need to adjust plasma density profiles and heat or drive current at various plasma radii - to move towards steady state operation and to suppress instabilities.**
**High energy (1 MeV D****-****) ion beams + radio frequency heating tuned to key plasma frequencies (ion - 40-56 MHz, electron cyclotron - 170 GHz, lower hybrid - 5 GHz);**
**RF systems modular and interchangeable in equatorial ports; EC used in upper ports to suppress neoclassical tearing modes;**
**2 main beamlines, with room for third; height adjustable +0.15 to - 0.42 m**
**Initial installation 73 MW with room for expansion to 130 MW (110 MW PS limit).**

- Steerable mirror

- Front shield

- Waveguides

- Windows

- Electron Cyclotron System Equatorial Port Plug

## Design - Diagnostics

- X-ray survey
- Imaging VUV Spectroscopy

- X-ray crystal spectroscopy
- Divertor VUV spectroscopy
- X-ray survey
- Core VUV monitor

- Divertor reflectometry

- Magnetic diagnostic coils

- Edge Thomson scattering

- Motional Stark effect
- Toroidal interferometer
- Electron cyclotron emission
- Wide-angle viewing/IR

- X-point LIDAR

**About 40 different diagnostic systems will be used.**
**Selected for endurance and nuclear compatibility.**
**3 groups: basic control, advanced control, physics studies.**
**Mostly designed and operated by Parties’ researchers.**

## Design - Tokamak Building

**Provides biological shield around cryostat to minimise activation and permit human access.**
**Additional confinement barrier.**
**Controls (with HVAC) contamination spread.**
**Provides shielding during remote handling cask transport.**
**Can be seismically isolated.**

**Tokamak Building - Equatorial Layout**

## ITER Site Layout

## Assembly

**Lower cryostat, tokamak gravity supports, lower PF and correction coils, TF pre-tensioning rings, etc., placed in the “pit”.**
**40° sectors of vessel + 2 TF coils, thermal shields, etc., assembled together on-site and moved to pit.**
**Sectors welded in opposition to minimise distortions.  TF coil pre-tensioning rings installed. Machine datum established.  Clean conditions in-vessel.**
**In-vessel components installed and aligned. PF/correction coils and cryostat above equator installed.  **
**External installations proceed in parallel. **

## Technology R&D

**Where new technologies or implementations were necessary, extensive R&D was carried out to prove its viability. Seven Large R&D Projects were established to demonstrate fabrication feasibility of major components of ITER. **

## Results of Magnet R&D

**Model coil results caused concern - 1.5K ****reduction in max. allowable operating temperature, where a margin of about 0.5K allowed for in the design. Due to high loading (70t/m) and unexpected strand deformation (or breakage?).**
**Benefits of low jacket COE material (titanium) not realised. **
**Better to standardise on stainless steel, and to increase strand critical current density  from 500-700 A/mm****2**** to 700-800 A/mm****2**.

**Fortunately coincides with increased performance strand now produced by industry driven mainly by accelerator programme.**

## Max. field 13.5T, max. current 46kA, stored energy 640MJ (max. in Nb3Sn)

**Max. field 13.5T, max. current 46kA, stored energy 640MJ (max. in Nb****3****Sn)**
**Ramp-up 1.2T/s (goal 0.4) and rampdown rates of -1.5T/s (goal -1.2) in insert coils, and 10,000 cycle test.**

## Welding radial plate cover plate

**Welding radial plate cover plate**

## Slide 48

## Divertor outer channel undergoing thermohydraulic tests.

**Divertor outer channel undergoing thermohydraulic tests.**

## Slide 50

## Dimensional accuracy after welding sector halves ± 3 mm

**Dimensional accuracy after welding sector halves ± 3 mm**

## Slide 52

## Slide 53

## Slide 54

## Positioning 0.5 mm and 0.1°, rail deployed 90° around torus in ~ 30 min..

**Positioning 0.5 mm and 0.1°, rail deployed 90° around torus in ~ 30 min.**.

## Slide 56

## Slide 57

## Current 80kA (above value needed in ITER and the maximum possible in the facility) with a field of 8T. 

**Current 80kA (above value needed in ITER and the maximum possible in the facility) with a field of 8T. **
**Highest current ever driven in a superconducting coil.**

## Blanket Option B

**Blanket Option B**