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April 13 & 14, 201 1 Workshop on EU fusion roa dmap -Garching 1 Contribution to EU fusion programme 2012 - 2020 Association EURATOM-MHEST Milan Čerček, HRU
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April 13 & 14, 2011Workshop on EU fusion roadmap -Garching 1 Contribution to EU fusion programme 2012 - 2020 Association EURATOM-MHEST Milan Čerček, HRU.

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Page 1: April 13 & 14, 2011Workshop on EU fusion roadmap -Garching 1 Contribution to EU fusion programme 2012 - 2020 Association EURATOM-MHEST Milan Čerček, HRU.

April 13 & 14, 2011 Workshop on EU fusion roadmap -Garching

1

Contribution to EU fusion programme 2012 - 2020

Association EURATOM-MHEST

Milan Čerček, HRU

Page 2: April 13 & 14, 2011Workshop on EU fusion roadmap -Garching 1 Contribution to EU fusion programme 2012 - 2020 Association EURATOM-MHEST Milan Čerček, HRU.

April 13 & 14, 2011 Workshop on EU fusion roadmap -Garching

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Contributions from SFA

• Objective 1 – Secure ITER operation

- EFDA: ITER physics

- EFDA: JET S/T

- EFDA: Public Information

• Objective 2 – Prepare “Generation ITER”

• Objective 3 – Fusion Power Plants

- EFDA: PPP&T

Page 3: April 13 & 14, 2011Workshop on EU fusion roadmap -Garching 1 Contribution to EU fusion programme 2012 - 2020 Association EURATOM-MHEST Milan Čerček, HRU.

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Support ITER construction

• F4E grants (consortia)- Nuclear data- TBM• F4E procurements• SME & SFA:- Cosylab, Ljubljana: CODAC (IO), Further interest in: instrumentation, plasma

control, remote handling…- LECAD, ULjubljana: special tools (EFDA

Technology TA - LOMAC)

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Secure ITER operation

• EFDA: ITER Physics• PWI: several areas, 8ppy

More specific to Microanalytical Center, Jozef Stefan Institute:

1 We are very much interested in continuing the coordinated studies of samples from tokamaks or other relevant experiments by ion beam analytical methods. Our experimental facility is continuously upgraded and we are providing ERDA and NRA techniques with macro (1mm) and micro (< 5 micrometer) beam besides other IBA methods. Restrictions.

2 A substantial construction project of incorporating an ultrahigh brightness multicusp H- ion source into our 2MV Tandem accelerator is under way. This will provide high brightness high energy H+ beam, high energy H0 and high brightness low energy H- beam for analytical purposes, surface reaction and material damage studies.

3 Interest in in-depth understanding of surface reactions which we can continue to study by in situ IBA methods ERDA and RBS. Even we have restricted our previous studies (and interests) to the interaction of neutral atomic hydrogen (H and D) with surfaces we can now extend similar studies to incident ions as we recently purchased a micro-wave sputter ion gun.

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• EFDA: ITER Physics• PWI: several areas (deposits removal) - Collaborations (CIEMAT, institutes outside of fusion programme)• The work has been focused on the problem of hydro-carbon

deposits. On one hand, we have been working on removing a-C:H deposits by means of neutral oxygen atoms (development of suitable reactors, experiments with mixed a-C/W:H deposits), while on the other hand we have been working on preventing the formation of a-C:H deposits with the scavenger technique.

• Both branches of research have yielded satisfactory results, so work in the near future will be aimed at further developing the researched fuel removal techniques.

• As new materials – candidates for PFCs – are developed (such as SiC/SiC), we intend to focus our research on their interaction with neutral H atoms, as well as verification of their compatibility with existent cleaning methods.

Secure ITER operation

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• EFDA: ITER Physics • PWI: several areas (fuel retention, fuel permeation)

Secure ITER operation

• Deuterium retention in Be-W mixed layers (ITER)• Tritium barriers for DEMO

- Selection of tritium permeation barrier materials should be revised since the last systematic reviews several new materials were synthesized and available data should be revised.- Barrier properties should be investigated regarding capability to be deposited over large areas.- They should be investigated by regular permeation tests at temperatures expected in DEMO.- Finally, the best candidate materials should be tested in radiation environments.

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• EFDA: JET S/T (3ppy)• Neutron transport modelling

– Neutron detector response– Shielding– Neutron activation studies– Breeding ratio

• Evaluation of nuclear data (F4E)• Uncertainties in neutron transp. calculations (F4E)

– Experimental uncertainties– Nuclear data uncertainties

Secure ITER operation

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• EFDA: Public Information (3ppy)

• FUSION EXPO Support Action

• PI in Associations- Permanent FUSION EXPO & lectures- together with NPP technolgy expo

at Nuclear Technology Training Centre- 8000 pupils/a- The activity should continue in the next decade!

Secure ITER operation

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Prepare “Generation ITER”

• 2005 – 2011: first generation PhDs (6) with fusion theses, post docs (JSI) at JET, at universities in UK, Germany, IPP

• 2012 – 2020: FUSENET, similar fusion oriented courses, summer schools

- only special subjects (general) at our unis and/or institute

- expectations: 15 – 20 during the whole decade

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Fusion Power Plants

• EFDA: PPP&T, committed to collaborate with 4->6 ppy/a

• Contribution to the development of DEMO divertor – numerical analyses

• Mid-term:  optimisation of TH performance & prediction of thermal stress

• Long-term: neutron irradiation effects, material degradation

• DEMO safety analyses (experience from NPP -30 years)

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Roadmap to fusion powerplantAnnex 3/II Input to Facilities Review Panel: Strengthening the

Materials R&D Programme (support 10 ppy/a)

Fusion Power Plants

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Non-magnetic ( no interaction with magnetic field)Resistant and mechanically stable up to 1200 °C ( high efficiency)Low-activation ( low radiactive wastes)No tritium retentionThermal conductivity

CVICVI

NITENITE

SITE (EU)SITE (EU)

SiC-based composite (not relevant for ITER and thus in background)

QQ: First Wall Blanket for DEMO: First Wall Blanket for DEMO (3ppy)(3ppy)

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Current state-of-art:SiCf/SiC

= 3D composite with β-SiC matrix and thermal conductivity >> 30 W/mK

To be done: optimisation testing

upscaling

Hybrid (W-SiC) routes:SiCf/(SiC-W)(W-SiC)f/SiC

To be done: ……..

SITESITE: : a process for forming fibre-reinforced ceramics

by slurry infiltration

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• Neutron transport modelling– Neutron detector response– Shielding– Neutron activation studies– Breeding ratio

• Evaluation of nuclear data (IAEA)• Uncertainties in neutron transport calculations

– Experimental uncertainties– Nuclear data uncertainties

• Nuclear safety

Fusion Power Plants