17 th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 1 B. Schunke D. Bora, J.-J....

17th IAEA TM on Research Using Small Fusion Devices , Lisbon B. Schunke1

B. SchunkeB. SchunkeD. Bora, J.-J. Cordier, R. Hemsworth, A. Tanga D. Bora, J.-J. Cordier, R. Hemsworth, A. Tanga

V. Antoni & RFX TeamV. Antoni & RFX TeamT. Bonicelli & EU NB groupT. Bonicelli & EU NB group

A. Chakraborty & IN NB groupA. Chakraborty & IN NB groupT. Inoue, K. Watanabe & JA NB groupT. Inoue, K. Watanabe & JA NB group

Negative Ion based Heating and Diagnostic Neutral Beams for

ITER

17th IAEA TM on Research Using Small Fusion Devices , Lisbon B. Schunke2 of 21

ITER

R=6.2 mIp=15 MA

Pfus=500 MW30 m

24 m


Neutral Beams for ITERNeutral Beams for ITER


• Introduction

• Negative Ion Beams for ITER– The Heating Neutral Beams– The Diagnostic Neutral Beam

• Neutral Beam R&D

• Summary and Outlook


Mission for H&CD systems for ITERMission for H&CD systems for ITERH&CD systems in ITER • must provide the tools necessary to achieve the

production of thermonuclear power and Q=10 and to demonstrate the feasibility of fusion power;

• demonstrate sufficient current drive (CD) capability to aim at steady state operation;

• provide additional “services” such as mode control, machine conditioning and assist in plasma start up and diagnosis;

• have the flexibility to insure effective and stable burn control.

IntroductionIntroduction


Operation scenariosOperation scenarios

• Plasma operation has been designed with variable combinations of heating and current drive systems: 2 (3) NB H&CD injectors 33 – 50 MW, 20~40MW ECH, 20~40MW ICH, 0~40MW LH; 3 MW ECH for start up, 3.5 MW DNB.

• ITER Baseline 2004: Start-up configuration requires 33 MW NB (2), 20MW ICH, 20MW ECH, 0MW LH; 3 MW ECH for start up, 3.5 MW DNB on Day1.

• The machine configuration is consistent with the possibility of implementation of various operating scenarios. Infrastructure for Heating systems has to be compatible.




DESIGN SCENARIOS FOR ITER OPERATION

Start up Scenario 1

ELMy Hmode

High ne

Scenario 2

ELMy Hmode

Low ne

Scenario 3

Hybrid scenario

Scenario 4

Steady State

Power

[MW]

No. of Equat. ports

Power

[MW]

No. of Equat. ports

Power

[MW]

No. of Equat. ports

Power

[MW]

No. of Equat. ports

Power

[MW]

No. of Equat. ports

NB 33 2 33 2 50 3 50 3 50 3 IC 20 1 40 2 20 1 40 2 20 1 EC 20 1 40 1 40 1 40 1 20 0 LH 0 0 20 1 20 1 0 0 40 2

Total Installed

73 4 133 6 130 6 130 6 130 6

ITER baseline scenarios foresee large (40%) contribution from NB heating,

3rd injector needed for scenarios 2-4


Power delivered to the plasma per injector

HNB (2 + 1)

16.7 MW

DNB

3.6MW (excl. duct losses)

Beam energy 1MeV (D-) / 870keV

(H-) 100 keV (H-)

Accelerated ion current 40 A (D-) / 46 A (H-) 60 A (H-)

Average accelerated ion current density

200 A/m2 (D-) / 300 A/m2 (H-) ****

300 A/m2

Current density uniformity over the extraction area

10 % 10 %

Pulse length ≤ 3600 s 5Hz mod. 1/6 ITER pulse

Beamlet divergence < 7 mrad < 7 mrad

Summary of the design parameters for heating and current drive (H&CD) & Diagnostic NBI system for ITER.

**** achieved 280 A/m2 of H for < 5s

Negative Ion Beams for ITER


The Injector can be separated in beam components (Ion Source, Accelerator, Neutralizer, Residual Ion

Dump and Calorimeter) other components (cryo-pump, vessels, fast shutter, duct, magnetic

shielding, and residual magnetic field compensating coils), bushing

The HNB injector

15m 5m

9m

Negative Ion Beams for ITER (HNB)

Weight >250 tons

Connected to tokamak via NB duct


DNB needed for Charge Exchange Recombination Spectroscopy (CXRS), only possibility to measure He density profiles in a tokamak (He ash); also self consistent code CHEAPCXRS cross sections of atomic transitions => beam energyGood S/N => High current density & beam divergence, beam

modulation

Negative Ion Beams for ITER (DNB)

Beam

Bushing PMS

Beam vessel

Upper correction

coils

Passive Magn. Shield

Same RF ion source, but simplified accelerator

But higher current density: material fatigue limitations


East

West

North

The NB injectors are installed in the equatorial level of the tokamak building: NB cell

NB directly connected to torus vacuum => high dose rate, high activation

Remote handling for interventions and maintenance

Temporary wall to allow installation of the 3rd injector

HNB#1

HNB#3

HNB#2

DNB



NB Power Supplies



All Heating and Current Drive systems are procured in kind

HNB and DNB ( EU & JA, IN )ICH & CD ( EU, US, IN )ECH & CD, Start up ( EU, JA, RF, IN )LHCD (no procurement package)

ITER IO provides integration

Department for CODAC & IT, Heating and CD, Diagnostics (CHD) – Director D. Bora (presentation Wednesday 9:00)

H & CD Division: Head A. TangaITER Man Power S.H. : Senior Technical Officers (3.5 of 5)

Phy/Eng : Technical Officers (9)Technical Assistants : (28)

R. Hemsworth (NB), B. Schunke (NB), B. Beaumont (ICH &LH), N. Kobayashi (ECH)

ITER relies on collaboration with partners, who have chosen to set up ITER in this form



ITER Research & Development BriefITER Research & Development Brief• H&CD systems must be built and installed in ITER

minimizing cost and risk in order to be on schedule and operate efficiently.

• H&CD systems are critical & essential for fusion research; hence critical technologies need to be developed for ITER and for DEMO.

• Pursue collaboration of the whole fusion community in the development and research in various areas related to H&CD systems.

• It is foreseen that following the initial operations, systems

will be upgraded during the operational phase of ITER.

=> applicable to NB systems

Neutral Beam R&D


Present plan for NB R&D Present plan for NB R&D (Host EU, but JA and IN part.)

• Establish Neutral Beam Test facility (NBTF) at Consorzio RFX, Padua, Italy (full 1MeV capability)

• The present plan is to start very early (tendering Jan 2008), the procurement of a full body of one injector and install in Padua for a total time of 10 years.

• Additionally there will be a second test line devoted to the development of the NB source, common between HNB and DNB, and the testing of DNB (possible in India).

• Non reusable items and special R&D will be supported by ITER R&D cash fund with a total sum of 8.8 kIUA.

• Building and services 31MEuros EU+Host• Manpower for detail design (EU-JA-IN 2007-2011) and

20-40 professionals for operations (EU+PTs TBN)

Neutral Beam R&D


ITER HNB – Neutral beam test facilty

Power supplyMaintenance

Experiment

Auxiliary systems

Cooling towers

Generic NBTF site layout

A full power 1MeV, 40A, D-, 3600 s test bed will be built at RFX, Padua, Italy

Neutral Beam R&D


MilestonesMilestones1. Start tendering Jan 20082. Shipping of High Voltage JA PS to test facility Jan 20123. Common testing of the HNB & DNB Ion source with

complete optimization for DNB Aug 2010 to 20134. Test of DNB start 2012 end 20155. Start HV tests Feb 2013 end 2017 6. Delivery schedule: Injector-1 will be assembled directly in

Cadarache by 2016 with inputs from R & D.Injector-2 in End 2017 from Padua. 7. DNB components are brought to Cadarache Jan 2016.Target: First ITER plasma end of 2016

Neutral Beam R&D


Additional (and possible future) support (non exclusive):Accelerator testing in 1MeV testbeds in CEA Cadarache, JAEA JAIon source development MPI, Garching, Germany ****Calorimeter design IN collaborated with NB Juelich, GermanyCryo-pump development, FZK Karlsruhe, GermanyNeutralizer Modeling, CNRS, FranceNegative Ion Source Modeling & Ion Source Diagnostics, Sofia

University, BulgariaWorldwide collaboration

Active support from CCNB (Coordinating Committee on Neutral Beams)

Create forum for exchange / workshop / meeting to accompany NB R&D

Neutral Beam R&D

**** Schroedinger Preis der Helmholtzgesellschaft 2006

Adopted as ITER reference ion source, DCR in 2007


Additional (and possible future) support (non exclusive):

• Basic physics studies of beam plasma interaction• Alternative ion source development (alternative to

caesium ?)• Alternative (optical) neutralizer design• Material testing• Development of neutral beam code• Beam plasma interaction physics

ITER Tasks, can be given to individual labs or DA, also ITER R&D fund for specific tasks

Neutral Beam R&D


Summary and Outlook (1)Summary and Outlook (1)Summary• Work in 2007 has concentrated on finalizing Baseline 2007• Procurement arrangement for the NBTF: power supply and

sources• NB cell design including Integration tasks:

– Finalize NB Cell lay-out– Installation sequence studies– Cooling requirements

Ongoing• Complete documentation and interface documents, e.g.

Plant breakdown structure (PBS); System requirements document (SRD)

• Implementation of the Design Change Requests from design review

• R & D in specific areas of all H&CD including NBs to meet Day 1 requirements


Outlook• Neutral Beam design freeze January 2008 so that the

detailed design phase can start.• Majority of procurement packages to be issued in 2008• NBTF full power testbed for NB issues in Padua, Italy:

collaboration of EU, JA, IN

Summary and Outlook (2)Summary and Outlook (2)

17 th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 1 B. Schunke D. Bora, J.-J....

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