ITER-TBM and Blanket Programs toward DEMO. Summary for Concluding Session€¦ · ITER-TBM and Blanket Programs toward DEMO. Summary for Concluding Session A. Ibarra (CIEMAT, Spain)

ITER-TBM and Blanket Programs toward DEMO.

Summary for Concluding Session

A. Ibarra (CIEMAT, Spain)R. Kurtz (PNNL, USA)

Objectives for this session

• What, how and when can be learned for ITER TBM projects?

• Role of other possible relevant facilities for DEMO blankets

• Oportunities for international collaboration

A. Ibarra; 3rd IAEA DEMO Programme Worskhop; Hefei, May 11-14, 2015

L. Boccaccini DEMO Blankets needs from ITER TBM ProgramY. Poitevin, A. Ibarra What can be measured in and what can be learned from EU ITER-TBMS. Chao Objectives of HCCR-TBA Testing Program in ITERH. Tanigawa Strategy of WCCB-TBM TBM Testing in ITERY. Strebkov, B. Kuteev What can be measured in and what can be learned from RU ITER-TBMP. Humrickhouse Tritium in DEMOS. Smolentsev MHD Modelling

Related posters:

P. Chaudhuri Design of LLCB TBM towards the Indian DEMO reactorK. Feng Progress on Design and R&D of CN HCCB TBM toward DEMOJ. Yu Design and R&D Progress of Breeder Blanket towards DEMO in China

Some general conclusions• TBMs are not fully DEMO relevant, but 1) it is the best

we can have, and 2) they are producing and will produce a lot of very relevant information

Outstanding technical challengeswith potentially large gaps beyond ITER

ITER will show scientific/engineering feasibility:– Plasma (Confinement/Burn, CD/Steady State, Disruption control, edge control)– Plasma Support Systems (LTSC magnets, fuelling, H&CD systems)

Most components inside the ITER VV are not DEMO relevant, e.g., materials, design. TBM provides can important information, but ...

• Most of the issues are common to any next major facility after ITER

DEMO Issues/gaps

For any further step, safety, power exhaust, breeding, RH and plant availability are important design driver and CANNOT be compromised

T breeding blanket technology (M4) Divertor design configuration and technology (M2 & M6)

Safety and licensing (M5)Plant design integration incl. BoP (M6)

Operating plasma scenario and control and efficient CD systems (M1)

Remote maintenance and plant availability (M6)

G. Federici, 2nd DCLL WS, 2014

A. Ibarra; 3rd IAEA DEMO Programme Worskhop; Hefei, May 11-14, 2015

6

Mission:The mission of the European TBM program is to test and validate during ITER operation the Helium‐Cooled Lithium‐Lead (HCLL) and the Helium‐Cooled Pebble‐Bed (HCPB) tritium breeding blanket concepts for application to fusion energy systems, with focus on DEMO.

Objectives:To meet this mission several “high‐level objectives” for TBM programme can be identified. They are:

Validation of the structural integrity theoretical predictions under combined and relevant loads Validation of the tritium breeding predictions Validation of tritium recovery process efficiency and T‐inventories in the blanket materials Validation of thermal predictions for strongly heterogeneous breeding blanket concepts with

volumetric heat sources Validation of the blanket power removal predictions Demonstration of the integral performance of the blanket systems.

Mission and objectives of the TBM Program

3rd IAEA DEMO Programme Workshop, 11‐15 May 2015, ASIPP (China)Y. Poitevin, A. Ibarra

Issues for blanket development and relationship with TBM testing

Issue Purpose Outcomes from TBM (inc. ITER)

TBR evaluation with high accuracy

To show ensuring TBR in DEMO

A unique environment for integrated demonstration

EM loads To show structural soundness in DEMO

Demonstration + practical plasma conditions

Irradiation effects in materials

To show structural/functional soundness in DEMO

Very limited demonstration(low fluence)

In-box LOCA To show structural soundness in DEMO

Direct demonstration will be difficult

Remote handling To show compatibilityin DEMO

Partial demonstration (different requirements are expected in DEMO)

Decay heat (LOCA)

To show structural/functional soundness in DEMO

Direct demonstration will be difficult

7/18H. Tanigawa

83rd IAEA DEMO Workshop, USTC, China, May 11‐14, 2015

HCCR‐TBS Testing Objectives and Test Plan

• Main objectives of 4 TBMs in different ITER Operation Phases

ITER Operation Phase

TBM Type Main Objectives

H‐He EM‐TBM(Electro‐Magnetic)

‐ To investigate the structural integrity under strong electromagnetic loads and high surface heat flux without neutron irradiation

D/DT(short pulse,low duty)

TN‐TBM(Thermo‐Neutronic)

‐ To validate neutron response data , thermal behaviours‐ To validate tritium breeding performance and nuclear design tools

D‐T (long pulse)

NT/TM‐TBM(Neutronic‐Tritium/Thermo‐Mechanic)

‐ To validate the tritium production and structural behavior at relevant temperatures‐ To investigate characterization of thermo‐mechanical behaviors of the pebble beds and tritium extraction by purge gas

D‐T(long pulse, high duty)

INT‐TBM‐ To evaluate the blanket capability on the tritium breeding, the extraction of high‐grade heat, the integrity under thermal, mechanical and electromagnetic loads

S. Cho

3rd IAEA DEMO Programme Workshopg, 11-15 May 2015, ASIPP (China) 9

Today1) We learn to built it!!! Return on experience(very important because the choice between different alternatives should notbe made based only on R&D results)

In the future1) We will learn on MHD issues2) We will learn on Neutronics issues3) We will learn on Tritium4) We will learn on EMBut all these topics requires modelling and measuring capabilities –now underdevelopment‐

What can we learn from the EU ITER TBM Systems?

Y. Poitevin, A. Ibarra



• Decision on DEMO Blanket can not be taken based only on R&D results. The technology expertise developed in the TBM programme will be essential

TBM Systems will test technological solutions

Concept studies and basic R&D are not sufficient to decide on selection/ranking of concept(s)

Need for ROX (Return On eXperience) − Implementation of regulatory obligations (e.g.

ESPN, waste disposal, etc.)− Methodology for integration of new

materials/fabrication in C&S− Involvement of Industry, cost− Availability (failures database)− Performances under tokamak actual and multi‐

loadings conditions (B, n, heat flux)

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HCLL-DEMO

HCLL-TBM

Test in ITER

The Test Blanket Module (TBM) Program in ITER is organizing the implementation & test of blankets technological solutions:− Test in tokamak (ITER)− Regulatory obligations (ITER nuclear plant, ASN)− Involvement of Industry; project budgetary

constraints; etc.

3rd IAEA DEMO Programme Workshop, 11‐15 May 2015, ASIPP (China)Y. Poitevin, A. Ibarra




• A critical role of the TBM programme is to produce data for models validation, but presently available models are not enough developed (at least for some aspects)

Where are we now in CMHD?

We are still pretty far from the target numbersS. Smolentsev


we can have, and 2) will produce a lot of very relevant information



• There are still missing basic critical modeling parameters

Tritium Solubility in PbLi• Tritium solubility in PbLi is low, and this will

tend to drive tritium into structural materials• Just how low is still rather uncertain; data

span several orders of magnitude• We need a better understanding of the

differences between these experiments and what may have caused them

E. MAS DE LES VALLS et al., Journal of Nuclear Materials, 376, 353 (2008).

PbLi

Solubility

Ta

10-6

10-5

10-4

10-3

10-2

10-1

100

101

102

103

104

105

0.9 1 1.1 1.2 1.3 1.4 1.5 1.6

Li(l)

Ti(s)

Nb(s)V(s)

Ta(s)

U(s)

Na(l)

Mg(l)

Ni(s) SS(s)Mo(s)

Cr(s)Sn(l)

Fe(s)Pt(s)

Cu(s)

Al(s)

Al(l)PbLi(l)

W(s)

1000 k/T

Hyd

ride

Form

ers

Interstitial Occluders

Ato

mic

ppm

H in

Met

al/P

a1/2

INL experiment- material appears to have segregated or reacted P. Humrickhouse


we can have, and 2) will produce a lot of very relevant information



• They are still missing basic critical modeling parameters• It is not clear if we know all the phenomena involved

Some general conclusions• Question marks about the “late” production of TBM

experimental results

Conclusions

TBM and DEMO Programme are in EU strong tied. TBM design is derived from DEMO/FPP studies and TBM results are to be used to confirm DEMO design.

Results of the TBM programme that can be used in EUROfusion-BB:• As the Roadmap foresees the blanket selection at the end of 2020, only

results of the design and R&D related to the TBM preparatory programme (not the TBM ITER test) can be used for that scope

• These results could include:• Safety and licensing framework for blanket as nuclear component.• Predictive tools in several key fields (EM, PbLi breeder cycle modelling, Helium

coolant and purge modelling, neutronics)• Manufacturing technologies with EUROFER• Diagnostics and measurement systems necessary in the R&D programme • Development and characterisation of functional materials

• The consideration of TBM in-pile results in the time frame 2021-2030 (preparation to the construction start in 2030) have not be analyses as far.

L.V. Boccaccini | 3rd IAEA DEMO Programme Workshop | Hefei | 11-14 May, 2015 | Page 18

L. Boccaccini

Warp-up discussion– Will be in any case the results of the different TBM relevant?– How we can choose between the different alternatives (criteria of comparison)?– Can it be made DEMO technical decisions before getting the ITER TBM results?– The results obtained by the experiments at the different TBMs will be enough or would it

be needed additional ones?– Are there any other area that should be included in the experiments to be made in ITER?– Do we have the required models available rigth now? Are being made enough efforts to

develop these models?– Which areas requires better development?– Do we know all the phenomena that must be model?– Are needed additional facilities to make this development faster?– Is it clear enough what parameters should be measured to allow this validation?– Will it be possible to get enough data for the validation (for example, from the point of

view of spatial resolution)– Do we have the appropiate sensor systems?– Feasibility of the extrapolation from ITER to DEMO– Concerns about the capability for the systems for T extraction– How the decisions for the different TBM choices were made?– Design window should be defined taking into account transient behaviour

Final conclusions and proposals for International collaboration

• General agreement ITER TBM programme produce a lot of results needed for the design of a DEMO Breeding Blanket, even if there are differences between them (“TBM sould be relevant for DEMO technology, not for DEMO configuration” S. Cho)

• Experimental programme is OK although it would be good to get results earlier

• It should be evaluated the possib ility to make Blanket-relevant experiments in IFMIF or in other facilities

• International collaboration for validation activities (for example, in the MHD area, on Tritium Transport modelling,…)

• International collaboration for the definition of agreed databases (for example on PbLi properties)

Ideas for the 4th DEMO Ws-ITo go deeper on the phenomena that could appear undercomplex environmental conditions:• Review of the present understanding of the possible

different “multiphysics” phenomena• Facilities to analice them• Modelling feasibility(multiple effects are not only MHD under B gradients of complex heating, but also similar issues that appear formany physical properties: i.e. permeation rates underionizing radiation and/or magnetic field, corrosion undermagnetic field, plasma erosion under magnetic field and radiation,…)

Ideas for the 4th DEMO Ws-IIDuring the last year (and in the near future) a lot of new developments are taking place in relation to the intense fusion-like neutron source.• A discussion on the of fusion-like irradiation needs

maybe could be interesting (involving materials people, but also design engineers, design code bodies,…)

• How much data are needed? What type of data? Fromwhat irradiation source?

• What be learned from other irradiation sources?• Are we able to extrapolate from different irradiation

conditions? (neutron-neutron, ion-neutrons,….)

Ideas for the 4th DEMO Ws-IIIDEMO licensing.A discussion involving Safety people, regulators, ITER expertise (and maybe the historical perspective of other projects) on what could be requirements and approach for DEMO licensing could be very interesting.

ITER-TBM and Blanket Programs toward DEMO. Summary for Concluding Session€¦ · ITER-TBM and Blanket Programs toward DEMO. Summary for Concluding Session A. Ibarra (CIEMAT, Spain)

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