the ifmif/eveda project - iaea na · 19 pascal garin iaea fusion energy conference, 13 october 2008...

IFMIF Engineering Validation and Engineering Design Activities

The IFMIF/EVEDA Project:Outcome of the first Engineering Studies

Pascal Garin, Masayoshi Sugimoto

on behalf of the Project Team

and all associated Institutes

–––

IAEA Fusion Energy Conference, Geneva, 13 October 2008


IFMIF Principles

Typical reactions7Li(d,2n)7Be

6Li(d,n)7Be

6Li(n,T)4He

IAEA Fusion Energy Conference, 13 October 2008Pascal Garin2

Accelerator (x 2)

14 MeV neutron equivalent irradiation effects

Test Cell

Low flux (< 1 dpa/an, > 8 litre)

Medium flux (20 – 1 dpa/an, 6 litre)

RFQ4 vanes

Out: 5 MeV

DTLHWR – 4 modules

9, 14.5, 26, 40 MeV

HEBTBeam shape:

200 x 50 mm2

InjectorECR – 140 mA

100 keV

Lithium target25 mm – 15 m/s

High flux (> 20 dpa/an, 0.5 litre)


High Performance Materials for Energy


First ReactorsCurrent Reactors

Advanced ReactorsFuture Systems

DEMO, Fusion Reactor

Strategic Missions:

• Electricity, Hydrogen, Heat

Strategic Missions:

• Electricity, Hydrogen, Heat

ITER, IFMIF

1-3 dpa1-3 dpa

1-3 dpa1-3 dpa

< 200 dpa< 200 dpa < 200 dpa< 200 dpa

< 150 dpa< 150 dpa

20-40/year20-40/year

Specific challenges for fusion:

• Short development path

• More demanding loading

conditions

Specific challenges for fusion:

• Short development path

• More demanding loading

conditions

1950 1970 1990 2010 2030 2050


Scope of Engineering Design

• Integration of elements provided by Working Groups

– Accelerator

– Lithium target

– Test Facilities

• Costing

– Of IFMIF (construction, operation and dismantling)

– Of construction planning

• Generic Site Safety Report

• Site Requirements and Site Design Assumptions

• Specifications of elements on the critical path



Scope of EVEDA phase: Validation(Engineering Validation and Engineering Design Activities)


~~

Accelerator Prototype (scale 1:1)

• Ion Source

• RadioFrequency Quadrupole

• First section Drift Tube Linac

• Building (at Rokkasho)

for the test of the acceleratorLithium Loop (scale 1/3)

• Diagnostics

• Erosion/Corrosion

• Purification system

• Remote Handling

High Flux Test Module (HFTM)

• Irradiation in fission reactor

• Validation of sample concepts

~~


Test of Prototypes in Japan


Rokkasho

Oarai

~ ~

Accelerator Prototype (scale 1:1)

• Ion Source

• RadioFrequency Quadrupole

• First section Drift Tube Linac

• Building (at Rokkasho)

for the test of the accelerator

Lithium Loop (scale 1:3)

• Diagnostics

• Erosion/Corrosion

• Purification system

• Remote Handling


DEMO Design and

R&D Center Building

DEMO Design and

R&D Center Building

IFMIF/EVEDA

Accelerator Building

IFMIF/EVEDA

Accelerator Building

CSC & REC

Building

CSC & REC

BuildingAdministration &

Research Building

Administration &

Research Building

Electrical

Power Station

Electrical

Power Station

The future Broader Approach Site at Rokkasho

IAEA Fusion Energy Conference, 13 October 20087 Pascal Garin


Pictures of the BA site (5 September 2008)



BA (Broader Approach) agreement between Japan and Euratom (5 February 2007)BA (Broader Approach) agreement between Japan and Euratom (5 February 2007)

Project Team

in Rokkasho, JapanOverall coordination

Interface

Integration

Project Team

in Rokkasho, JapanOverall coordination

Interface

Integration

Organization and Contributors


International Fusion Materials Community (Users)International Fusion Materials Community (Users)

Steering CommitteeSteering CommitteeJapanJapan EuratomEuratom

JAEA (IA)JAEA (IA) F4E (IA)F4E (IA)Procurement ArrangementsProcurement Arrangements

Project LeaderProject Leader

Main Contributors in EUMain Contributors in EU

Main Contributors in JapanMain Contributors in Japan

Voluntary Contributors

F, D, I, S, Ch, (B)

Voluntary Contributors

F, D, I, S, Ch, (B)

Outside of BA activities (e.g. IEA Fusion Materials/ Working Group on Irrad. Facil. & Testing)

IFMIF/EVEDA

Project Committee

IFMIF/EVEDA

Project Committee

Commitment Commitment

Witn

ess


Main progress of the project since June 2007

• Accelerator– Beam dynamics well advanced, HEBT still to be done

– RFQ preliminary design review in June 2008

– Proposal of superconducting HWR DTL accepted

– RF power system concept is revised

– Construction of the accelerator prototype building started

• Lithium Target– Conceptual design completed

– Hybrid bayonet concept implemented in the prototype

– Detailed engineering design of prototype starting

– Strategy for lithium purification established (first experiments promising)

• Test Facilities– Target and Test Cell being fully re-designed

– New concept of High Flux Test Module

– First engineering design of Creep Fatigue Test Module

– Conceptual activities for the Tritium Release Module



RadioFrequency Quadrupole


Design Parameters• Input energy: 100 keV

• Output energy: 5 MeV

• Input emittance RMS: 0.25 mm mrad (norm.)

• Max surface field < 25.2 MV/m (1.8 kilpat)

• RFQ End Phase advance: ~ 220°/m trans.~ 90°/m long.

• Frequency: 175 MHz

• Input Current: 130 mA

• Particle: Deuteron

Transmission = 98.5 %

Power Loss = 385 W

Almost all loss below 1 MeV

Shaper GB Accelerator

9.78 m

Pumping

RF Couplers

Tuners

1.1 m

Δf:

-0.52 kHz


Overall Layout for IFMIF – Overview of DTL


42.0 m

22.5 m

Reduction of the length by 10 m


Proposal of Test for EVEDA



New RF Power System proposal

• Simplification of RF sources

– Two chains required

• 105 kW Units

• 220-230 kW Units

– Standardization

• Improvement of reliabilityIAEA Fusion Energy Conference, 13 October 2008Pascal Garin14

3.5 m

1.0 m


Lithium Target: Principle of the Loop

• Main specifications

– Heat Flux by Beam: 1 GW/m2

– Lithium Flow Speed: 15 m/s (range 10 – 20)

– Width / Thickness of Li Flow: 26 / 2.5 cm

– Inlet, Outlet, Peak Temperatures: 250, 300, 450 °C

– Impurity level: 10 wppm (C, N, O each)


Dump Tank

Purification System

ColdTrap

Quench

Tank

N -HotTrap

H -HotTrap

Main Li Loop

Target Assembly

Back-

Plate

Off-line

Monitors

H

X

EMP

On-line

Monitor



20025

1000

600

1400

20151050

Depth (mm)

Saturation Temp

RW=100 mm

1000

Li

250

344°C

280°C

408°C

Temperatures Distribution in Li

Flow (U0 = 20 m/s)

3mm

712°C

Te

mp

era

ture

(°C

)

Contour of Li temperaturein beam heated region (Tin = 250°C)

Neutron

Backwall

Be

am

He

igh

t (5

0m

m)

Flow

Free

Surface

Thermo-Fluid Analysis of Li Flow

Centrifugal force by concave backplate increases

saturation temperature around 1000 °C in Li flow

250.1°C

250°C

310°C

270°C

290°C


Erosion/Corrosion

• Lifus 3 loop commissioned

• First test of 1,000 hrs with 316L and Eurofer done

• Three traps (cold, Ti –hot, Y-hot) manufactured

IAEA Fusion Energy Conference, 13 October 2008Pascal Garin18 Lifus 3 loop

• Lithium velocity: 16 m/s max.

• Temperature: 450 °C max.

• Temperature difference: 30°C min.

• Lithium content: 42 liters

EMP

Air Cooler

Heater

Drain

Economizer

Test Section


Nitrogen Gettering

• Fe-7.5%Ti Alloy Plates

• Temperature: ~600°C

• Oxygen getter

• Flow rate: ~4 cm/s

• After 1000 h immersion

in the loop, a small

weight loss is observed

(0.013 g/m2.h)


Cooling area

(3～400�)

Warming area

（～600�）

Mo crucible S.S. pot

Rotation inducer

S.S. shaftEr powder as O getter

Fe-Ti alloy is compatible even in flowing lithium with thermal gradient.


Principle of Test Modules


2 m

D+

Medium Flux

Test Modules

High Flux

Test Module Low Flux

Irradiation

Tubes

Lithium

Target

Lithium Tank

Shield plug


New design of Test Cell under consideration


Controlled and separated atmospheres

11

22

33

33

44

1: Beam / Target

2: TTC interior

3: Safety Zone

4: Access Cell

1: Beam / Target

2: TTC interior

3: Safety Zone

4: Access Cell

1: High vacuum

2: Vacuum (Ar, He)

3: Ar (He)

4: Air

1: High vacuum

2: Vacuum (Ar, He)

3: Ar (He)

4: Air


Evolution of the HFTM Design 2007 to Mid 2008

• Cut free lateral reflectors, de-couple the massive reflectors from the fragile zone

• Rig-like reflectors, resulting in a 8x3 modular design + irradiation volume (tungsten),

mechanical advantages

• Introduction of individual feed lines per compartment to control mass flow

• Introduction of a symmetric „horse shoe“ shaped support and feed structure

• Flexible mounting of the mechanically separated container zone


stiff feed lines and

attachment frame

stiff feed lines and

attachment frame

flexible piping connectionflexible piping connection

stiff connection of

container to frame

stiff connection of

container to frame

4x3 irradiation rigs4x3 irradiation rigs

solid lateral reflector solid lateral reflector solid lateral reflectors solid lateral reflectors

2x3 companion rigs2x3 companion rigs

4x3 irradiation rigs4x3 irradiation rigs

2x3 companion rigs2x3 companion rigs


Horizontal Set-up (Japan)


neutron flux

coolant flow (He)

200

50

50

[mm]

Heater-integrated plate and capsule

Horizontal set-up HFTM

plate heater(for temperature

control)

cast-type capsule(the same material

with specimens is

preferred)

Thermo-couple

specimens

Objective: To provide the full detailed engineering

file of HFTM (Horizontal set-up).

Objective: To provide the full detailed engineering

file of HFTM (Horizontal set-up).

Project Plan:

1. Conceptual design of heater-integrated plate

and capsule (H-I).

2. Fabrication and basic performance tests of

model of H-I

3. Engineering design of prototype of H-I

4. Performance tests of prototype H-I in He loop

5. Engineering design of full scale HFTM

Project Plan:

1. Conceptual design of heater-integrated plate

and capsule (H-I).

2. Fabrication and basic performance tests of

model of H-I

3. Engineering design of prototype of H-I

4. Performance tests of prototype H-I in He loop

5. Engineering design of full scale HFTM


Creep Fatigue Test Module


Actuator

Loading frame

Heat generating body

Specimen

The CFTM consists of 3 test machines

mounted in parallel and able to run

3 independent mechanical tests.

Helium mass flow: 0.2 g/s


Summary

• Main concepts resulting of the previous phases of IFMIF

have been confirmed

• Several important modifications were brought

– Accelerator Facility: main accelerator design was changed from the

room-temperature Alvarez DTL to the superconducting HWR system

– Lithium Target Facility: lithium purification techniques are being

developed further from the preparatory phase before starting the BA

– Test Facilities: several Test Cell arrangements are being developed

• In conclusion, no showstopper has been identified and the

future work will concentrate on the prototype detailed

design and start of manufacturing, keeping the objective of

IFMIF engineering report deadline of June 2013


the ifmif/eveda project - iaea na · 19 pascal garin iaea fusion energy conference, 13 october 2008...

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