European Roadmap to Fusion Energy · despite-renewables-surge. 2 F. Wagner, Eigenschaften einer...

European Roadmap to Fusion Energy

Tony Donné

Programme Manager EUROfusion

SOFT 2018| Giardini Naxos, IT | 17 Sep 2018

A.J.H. Donné | SOFT, Sicily, IT | 17 September 2018

Some lessons from Germany:

• Germany subsidises wind and solar with ~25 billion Euro per year

• Wind and solar energy contribute on average to ~35-40% of the electricity generation

• On a windy day energy prices go negative as Germany produces more than it needs

• There are people who believe that wind and solar can completely take care of the CO2-transition by 2050

Do we need fusion electricity?

Source: Energycharts.de


Some lessons from Germany: • However, CO2 emission due to

electricity generation doesn’t go down1

• Recent studies show that even with storage and EU super grids, intermittent sources as wind and solar can’t contribute more than 50-60% to the electricity needs2,3

• Large scale back-up energy sources

are needed! • Nuclear being the only option to

replace fossils and to reduce the CO2 emission

• Fusion is one of the nuclear options, and its potential utilisation should be pursued with vigour

Do we need fusion electricity?

1 www.cleanenergywire.org/news/german-co2-emissions-rise-2015-despite-renewables-surge.

2 F. Wagner, Eigenschaften einer Stromversorgung mit intermittierenden Quellen, Proc. Deutsche Physikalische Gemeinschaft, Arbeitskreis Energie, Berlin, 138-155 (2015).

3 H.W. Sinn, Buffering volatility: a study on the limits of Germany’s energy revolution, http://www.nber.org/papers/w22467

Source: Clean Energy Wire

Note: Fusion is not in competition with other renewables. It is needed as back-up and as part of the energy mix


FUSION WORKS

The sun and the stars shine thanks to fusion reactions taking place in their core. To make fusion work on Earth we need to overcome a number of challenges. The Fusion Roadmap is the master plan how to solve the challenges and achieve electricity from fusion

Image: NASA


FUSION ROADMAP

DEMONSTRATE FUSION ELECTRICITY EARLY IN THE SECOND HALF OF THE CENTURY • Based on a number of technical

assessment reports • Provides coherent EU programme with

a clear objective • Avoids open-ended R&D


Short-term Medium-term Long-term

Milestone

Fusion Roadmap animated

Lower cost through concept improvements and innovations

Fusi

on

Po

wer

Pla

nts

Stellarator as fusion plant?

Material research facilities IFMIF/DONES

DEMO

Consistent

concept

Commence

construction

Electricity

production

ITER

First plasma Full performance

Research on

present and

planned

facilities,

analysis and

modelling


Plasma Regimes of Operation

Heat-Exhaust Systems

Neutron Resistant Materials

Tritium Self-

Sufficiency Implemen-tation of Intrinsic Safety

Features

Integrated DEMO design

Competi-tive cost of Electricity

Stellarator

3MA ILW

(2016)

2018/19 Objective

JET-C until October 2009

JET-ITER-Like Wall since May 2011

Roadmap Missions


Mission 1 & 2


JET, UK

TCV, CH

JT-60SA, JA (Start in 2020)

ASDEX Upgrade, Munich, DE

ITER (Our target device)

MAST Upgrade, UK (Start in 2019)

Tokamak devices


JET – THE WORLD’S LARGEST TOKAMAK

Unique ITER-Relevance: • Be-wall, W-divertor • Can operate with DT • Equiped with Remote Handling • Closest in performance

Image: EUROfusion, CC BY 4.0, www.euro-fusion.org

JET – The present flagship


JET’S HIGHLIGHTS

• The first tokamak to achieve controlled deuterium-tritium fusion power (1991)

• The only device currently capable of using deuterium and tritium fuel

• World record of 16 megawatts of fusion power (1997). This proved that large amounts of power can be produced from fusion; results can be scaled up to ITER and power plants.

Graphic: EUROfusion, CC BY 4.0, www.euro-fusion.org

Projection for 2020

JET – DT Operation


Devices to study the behaviour of plasma facing components

Plasma Facing Component Testing


World record exposure in MAGNUM-PSI

ITER relevant conditions (~1 Full Power Year):

Target 1200 C

Heat load 20 MWm-2

Particle load 1.5 1025 particles m-2s-1

Duration: 18,5 hours


Plasma Exhaust – newly funded upgrades

Upper divertor in ASDEX-Upgrade

Baffles and cryopump in TCV

NBI and Divertor diagnostics for MAST-Upgrade

JULE-PSI and JUDITH-3

Actively-cooled divertor in WEST


Plasma Exhaust – 2 new national projects

Divertor Test Tokamak (Italy) COMPASS-Upgrade (Czech Republic)

EUROfusion might get involved in the future in these devices*: • to test an alternative divertor on DTT • To test a liquid metal divertor in case of COMPASS-Upgrade

* Pending progress with the projects and outcomes of feasibility studies


Mission 3


Frac

ture

Me

chan

ics

V. Nikolic, ÖAW

Cu-W(fiber) composite tubes

A. v. Müller, J.-H. You, IPP

ErOx

ErOx/W

ZrOx

ZrOx/W

W-W(fiber) composite

J. Riesch, J.-H. You, IPP J.W. Coenen, FZJ

High Heat Flux Materials


Refractory Materials for DEMO Divertors In close cooperation with Plansee company

Severe cold-rolling makes W ductile

Hot-rolled, coarse-grained W

Test temperature: RT

Severely cold-rolled, ultrafine-grained

W; Test temperature: RT

10 mm 10 mm

J. Reiser et al., Int. J. Refract. Met. Hard Mater. 64 (2017) 261–278

Ductile tungsten


IFMIF-DONES

Principle

Prototype accelerator (with/in Japan)

Building


Mission 4 - 6


DEMO Demonstration reactor to deliver for the first time fusion electricity to the grid


• provide a starting point for safety analyses and further design improvements;

• identify areas with significant uncertainties;

• early substantiation of RH to limit redesign risks.

Initial integration studies with the support of a “nuclear architect“ to:

• develop a technically feasible, operable, and maintainable plant design;

• identify the major structures needed to contain plant equipment;

Preliminary DEMO Plant Layout

DEMO Tokamak Building Complex (compared with EPR)

C. Gliss, W. Korn (Framatome): to appear in Fus. Eng. Des.


Site Services

Integrated DEMO Design

Plasma

Vacuum

Fuelling

Heat* Extraction

Plasma Heating

Current Drive

Plasma Control

Exhaust

1st Confinement

2nd Confinement

Maintenance

Power* Generation

Plasma Confinement

Cryocontrol

Plasma Facing

Shielding Tritium Breeding*

Waste Mngmt

PIS

System-of-systems (SoS):

• A set or arrangement of interdependent systems that are related or

connected to provide a given capability.

• The loss of any part of the system will degrade performance

capabilities of the whole.

• Optimising individual systems does not lead to overall optima.

• Exhibits emergent behaviour not otherwise achievable by the

Constituent Systems.

• The complexity of dependencies between systems increases

significantly once we move to their physical embodiments.


Burn scenarios, Bootstrap fraction, Full plasma control incl. helium and impurities , First wall heat loads,, Exhaust at high power Tritium plant validation, Full H&CD and fuelling validation

2014-2020 Preconceptual

Design

2020-2027 Concept Design

2029-2038 Engineering Design & Site

Selection

2040-2051 Procurement & Construction

2051-2060 Commissioning & Operations DEMO Schedule

2020 pre-CDR Gate

2027 CDR Gate

2038 Decision to Construct

2060 2039 2037 2035 2033 2029 2025

ITER Schedule

2025

2014

2025-26 First

Plasma

2026-2028 2nd Assembly

2028-2030 Pre Fusion

Operation 1

2030-2032 3rd Assembly

2032-2034 Pre Fusion

Operation 2

2034-35 4th

Assembly

2035-2040 High Power Operation

2040

2038-2040 EDR

Consol

2027-2029 CDR

Consolid.

Operation with Low Heating

Installation of: First Wall, Divertor, Neutral Beam Remote Handling, Pellet injector, DMS hardware commissioning

Low Power Operation (Hydrogen & Helium)

Installation of: ICRH & NB, ELM control system First TBM modules Tritium Plant

High Power Operation (Hydrogen & Helium)

Tritium Plant Commissioning

High Power Operation (Deuterium-Tritium)

Validated Assembly, Integrated Design, Testing & Commissioning, SC magnets, VV fabrication validation

Integrated diagnostics validation, ECRH performance, Disruption characterisation, Divertor remote maintenance validation

H-mode transition threshold, Validation of ELM control & disruption mitigation, NB & ICRH performance, Diagnostics validation, Validation of TBM fabrication

TBM Validation, Operational scenario refinement, Q=10 (short pulse)

Long pulse) burning plasma

ITER developments of relevance to DEMO design - examples


Development of DEMO design options and related R&D

Solutions/ opportunities


Key risks

Risks

Focus: Answer critical questions Focus: De-risk concept

Pre-conceptual design Conceptual design Engineering design 2020 2027 2029

Ad

dit

ion

al D

EMO

R&

D

Engi

ne

eri

ng

Pro

gram

me

Critical questions

Developing and selecting design options

(architecture, divertor options, breeding blankets)

Focus: Mitigate key risks


Baseline architecture selected Driver/advanced blanket selected

Selection exhaust options H&CD mix selection

DEMO Baseline design

DEMO Backup design

Pre-CDR CDR ED

A P

rep

arat

ion


Costs of change to a system

[Source: INCOSE UK, Z3, Issue 3, March 2009]

Freezing of design options should be done in a very careful way – changing a design at too late a stage increases the costs


Mission 7


High Current HTS Cables for Fusion and more (1)

Performance of HTS material REBCO is superior and increasing fast

Industrial available REBCO can provide large temperature margin even at highest magnetic fields

REBCO performance has increased drastically in the last years

But REBCO is available as thin tapes, only.

How to form high current cables from such tapes?



Cable concepts focus to round forms and twisted stacks of REBCO tapes are mainly the base

Takayasu (MIT)

Uglietti (SPC)

Good idea!

Can this approach be optimized ?

higher current (more superconductor)

mechanical stability (no soldered Cu half shells)

easy manufacturing including twist

HTS CrossConductor “HTS CroCo" formed from tapes with two different widths



HTS CroCo fabricated with 8 m length!


Attachment Neutron Shield

MMS Blanket

MMS Transporter Transport Casks Revaluation of the in-vessel remote maintenance:

• Improve flexibility allows for more cooling systems and access for diagnostics H&CD.

• Independent blanket and divertor maintenance

• Improved maintenance durations

• Near vertical lifts for blankets increase robustness of remote handling equipment

• Includes a neutron shield plug

• Independent port closure plate

• No in-vessel mover

• ITER-like cask transportation

• Improved unplanned single blanket maintenance

Lower the costs of fusion electricity

Remote Maintenance


Mission 8


First Plasma in W7-X (Greifswald)

Wendelstein 7-X

from assembly to operation

12.05.2014: Start of commissioning

16.07.2015: First flux surface measurements

09.12.2015: Operation permit granted

10.12.2015: First helium plasma

03.02.2016: First hydrogen plasma

< 10.03.2016: First experimental campaign

(W7-X Team = IPP, EUROfusion, US, Japan)

HELIAS-type stellarator

• Nf=5, R/a = 5.5m/0.53m

→ ~30 m3 plasma volume

• 50+20 superconducting coils (2.5T)

• ~8+7MW (ECRH, NBI) + ICRH (later upgrades)

Wendelstein 7-X Max-Planck-Institut für Plasmaphysik

Greifswald (Germany)

© IPP

© IPP

First plasma in W7-X

© M. Otte, IPP

Experimental demonstration of closed flux surfaces


The End

The realisation of fusion electricity is feasible EUROfusion coordinates the Fusion R&D in 28 European countries The roadmap is the master plan that prioritises how to tackle the challenges to get as soon as possible to fusion electricity

European Roadmap to Fusion Energy · despite-renewables-surge. 2 F. Wagner, Eigenschaften einer...

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