Li Puma - Advanced Projects Homepage

DESIGN AND DEVELOPMENT 

OF DEMO BLANKET 

CONCEPTS IN EUROPE 

L.V. Boccaccini, C. Bachmann, G. Federici, Antonella Li Puma, 

P. Norajitra, 

Acknowledged contributions from: G. Aiello (CEA), J. Aubert (CEA), 

L. Bühler (KIT), A. Ciampichetti (ENEA), D. Demange (KIT), 

N.Jonqueres (CEA), J. Konys, W. Krauss (KIT), A. Morin (CEA), 

C. Mistrangelo (KIT), C. Petesh (CEA),… 

16 OCTOBER 2012 

| PAGE 1 

1st IAEA DEMO Programme Workshop, 

UCLA, 15-18 Oct. 2012, A. Li Puma et al.

ied 

ed 

de 

out 

SUMMARY 

Reference EU breeding blanket concepts for testing in ITER and DEMO 

relevancy of TBMs 

European Fusion Design Agreement Development Programme 

Blanket concepts design and relevant R&D issues/activities 

WCLL blanket 

HCLL blanket 

HCPB blanket 

DCLL blanket 

Common R&D Activities 

Conclusions 

1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. | PAGE 2

1st IAEA DEMO Programme Workshop, UCLA, 

15-18 Oct. 2012, A. Li Puma et al. 

| PAGE 3 

REFERENCE EU BREEDING BLANKET 

CONCEPTS FOR TESTING IN ITER AND 

DEMO RELEVANCY OF TBMS 

This work, supported by the European Communities under the contract of 

Association between EURATOM and the TBM-CA, was carried out within the 

framework of Fusion for Energy TBMs development. The views and opinions 

expressed herein do not necessarily reflect those of the European 

Commission.

HCLL TBM 

L.V. Boccaccini et al. 2011 

HCLL/HCPB TEST BLANKET MODULES 

HCPB TBM 


DEMO RELEVANCY OF THE 

HCLL/HCPB TBM R&D PROGRAMME 

Conceptual design of the TBM 

! Maximum geometrical similarity with DEMO modules. 

! Compliance with regulation 

! Neutronic, thermo-hydraulic and structural analyses 

! Integration of sensors 

! Relevant in direction to DEMO. 

Manufacturing 

! development for EUROFER TBM structures (plates 

with cooling channels) and joint technology. 

! Relevant in direction to DEMO. 

! Large procurements started in 2012. 

Eurofer97 subcomponents mock-ups 

1:3 FW mock-up: pre test ior 

diffusion welding. Rey, von der 

Weth, Neuberger (KIT), 2012. 

Total von Mises stresses at 

flat top Cismondi, 2011 

VM primary stresses in case of 

accidental pressurization of the 

box, Aiello 2011 

Thermomechanical cycling of 

the FW, Aiello, 2011 


DEMO RELEVANCY OF THE 

HCLL/HCPB TBM R&D PROGRAMME 

Material development, characterisation and 

procurement 

! 

Safety 

study of accidents related to the TBM operation. 

! Structural (EUROFER), and functional (Li4SiO4, Li2TiO3 R&D ITER specific, but with interesting topics 

Be-alloy pebbles, LiPb, coatings) materials. Objective: 

test in ITER of DEMO relevant materials. 

like interaction of water with Be or PbLi. 

! PIE of large irradiation programme (e.g. HICU and 

HIDOBE for solid breeder materials and Be, LIBRETTO 

for LiPb) are ongoing. 

He cooling 

! He circuit not relevant for DEMO. Conceptual design in 

advanced status. 

Predictive tools 

! Experimental and modeling programme to validate 

computational tools through TBM data and to extrapolate 

them to DEMO. 

Instrumentation 

! Requirements mostly dictated by TBM test Programme. 

! Some technologies for C&M can be used in DEMO. 

Tritium recovery 

! T-auxiliary systems mostly not relevant to DEMO 

systems. Conceptual design in advanced status 

RELAP 5, ANSYS and MELCOR models for combined exvessel 

LOCA analyses, Xue Zhou Jin, in print 

Examples of instrumentation layout, 

Li Puma 2010 FED, Aiello IAEA 2012 


THE TBM EXPERIMENTAL PROGRAMME 

AND EU BB TESTING FACILITIES 

! List of possible experiments: electromagnetics, neutronics, tritium generation/extraction, MHD, corrosion, etc. 

! Preliminary work-plan aimed at filling the gap between the present R&D level and the required one defined. 

! Experimental campaigns undergoing in several EU laboratories. 

PbLi loop at IPUL for corrosion 

experiments. 

The TRIEX loop at 

ENEA for the 

development of the 

TEU 

The MEKKA facility at KIT 

NaK loop for MHD experiments 

The CASPER facility 

at KIT tritium 

laboratory 

(tritium accountancy) 

The DIADEMO facility 

in CEA for 

thermomechanical 

testing of 

subcomponents 

The HeFus3/EBTTF 

Facility in ENEA for 

thermomechanical 

testing of full-scale TBM 

mock-ups 

The HEBLO/HETRA facility at KIT 

for investigation of heat removal 

from the FW 




| PAGE 8 

EU DEVELOPMENT PROGRAMME

DEMO TOP LEVEL REQUIREMENTS 

(DEMO AHG/ F4E GB AND CCE-FU) 

DEMO presently conceived to be the single step between 

ITER and a commercial reactor 

It is rather difficult, to define a set of top-level 

requirements for a device like DEMO without specifying 

beforehand a large set of hypotheses, both in physics and 

in technology. However, a definition of the AHG is to 

! Demonstrate a workable solution for all physics and 

technology questions 

! Demonstrate significant net (~ several hundreds of MW) 

electricity production with self-sufficient fuel supply. 

! Demonstrate high availability and reliability operation over 

a reasonable time span. 


REVIEW OF PREVIOUS EU STUDIES 

! Work carried out in the past in Europe on fusion reactor design 

focussed on the assessment of the safety, environmental, societal 

and economic features of fusion power, and less on feasibility studies 

[European Power Plant Conceptual Study (PPCS)]. 

! PPCS – completed in April 2005: study of conceptual designs of five 

commercial fusion power plants and the main emphasis was on 

system integration. 

! It focused on a # of power plant models illustrative of a wider 

spectrum of possibilities. 

! All based on the tokamak concept ~ and 1500 Mwe electrical output 

! These span a range from relatively near-term, based on limited 

technology and plasma physics extrapolations, to advanced 

concepts. 


BLANKET CONCEPTS 


FEASIBILITY CONCERNS 

NO-ONE IS PERFECT! 

Concerns HCPB HCLL WCLL DCLL 

Tested in ITER TBM ☺ 

Suitability for Eurofer 

FW heat flux capability 

Safety issues of coolant 

Technology readiness: blanket / BoP / / / / 

Potential for high coolant outlet temperature 

High coolant pumping power 

Thermal deformation of blanket ( dT of coolant) 

Electrical conductive breeder ( EM loads) 

Shielding efficiency/ n-streaming void space 

Activation products in coolant (water) 

Tritium extraction from breeder 

Tritium extraction from coolant 

Tritium permeation through heat exchanger 

A selection now is premature!! 


EU DEMO DESIGN OPTIONS 

BALANCING DEVELOPMENTS AND TIMESCALE 

! EFDA PPPT 2013 is focused on the analysis of the design requirements and technical 

prerequisites of a DEMO reactor. 

! As part of the EFDA PPPT WP 2011-13 a # design options is being analysed. 

“conservative baseline design” or “early DEMO” concept 

deliverable in the short to medium term 

! inductive/cyclic (modest volume power density) 

! construction to be started in ~ “20 years from now”; 

! based on the expected performance of ITER with reasonable improvements in science 

and technology; 

“optimistic (advanced?) design”, - a DEMO concept 

! based around steady state and more advanced physics assumptions which are at the 

upper limit of what may be achieved in ITER phase 2; 

! Technology (and particularly materials) advances which will require extensive 

validation efforts. 

! longer term. 


STARTER BLANKET IN DEMO 

! High component reliability will be a main design driver for DEMO 

simplified designs, established technology, qualified materials also for BoP 

components. 

! DEMO phase 1 of operation: ‘starter components’ (blanket and divertor) 

designed for ~20 dpa at the first wall (and ~5 dpa at the divertor). 

! Second phase: FW steel irradiated up to 50 dpa. 

! Same coolant for the two phases of DEMO, since deemed unfeasible. 

! Testing ports for qualification of more advanced concepts of blanket and 

divertor. 

! Vacuum vessel: low dose environment, proven materials and technology. 


BLANKET AND FUEL CYCLE TRL 

Readiness Now 

Readiness after ITER 

Fuel cycle and tritium accountancy 

(TRL 6) 

Blanket breeding control (TRL 6) 

T-breeding and power extraction 

control (TRL 6) 

Tritium recovery (TRL 4-5) 

Fuel cycle and tritium accountancy 

(TRL 4) 

Blanket breeding control (TRL 3-4) 

Tritium recovery (TRL 3) 

T-breeding and power 

extraction (TRL 2-3) 

TRL = Technology Readiness Level 


MISSION 4: TRITIUM SELF-SUFFICIENCY AND 

FUEL CYCLE TOP LEVEL RISKS/ RISK MITIGATION 

RISKS RISK MITIGATION STRATEGY 

• DEMO blanket 

concept differs from 

concepts tested in 

ITER TBM 

• Insufficient TBM 

design data (e.g., 

very low n-dose) 

• Inadequate T- 

extraction efficiency 

from LM breeders 

blankets 

• Unacceptably high 

tritium permeation 

• Develop/demonstrate feasibility of alternative designs (e.g., WCLL) 

• Qualification of mechanical, thermal hydraulic performance in a 

non-nuclear environment (facility) 

• Share information on the TBM programme among ITER parties 

• Participate to operation of a nuclear device if built by an ITER party 

(e.g., tests in CFETR) 

• Additional tests in fission reactors. 

• Qualification of mechanical, thermal hydraulic performance in a 

non-nuclear environment (facility). 

• R&D on T-extraction from PbLi loops 

• Demonstrate feasibility and determine performance of the vacuum 

permeator concept under relevant operating conditions. 

• Develop improved high radiation resistance T permeation barriers. 

• Control of tritium through non-traditional tritium-handling equipment 

(heat exchangers; long high-temperature pipe runs, etc). 


Area R&D investment 

Blanket manufacturing 

(small/medium-scale mock-ups). 

Blanket performance (DIADEMO (CEA), EBBTF 

(ENEA), HeFUS 3 (ENEA)+ new? 

R&D on Breeders/ Multipliers 

(Fission reactors: HFR (NL), HFIR (ORNL), JH (FR), 

BOR-60 (Russia), BR-2 (MOL), BRR (KFKI, H), LVR-15 

(CZ), OSIRIS (CEA) 

Safety (WCLL)/ LiPb Eurofer compatibility/ 

corrosion LIFUS-5 (ENEA), RELA (III), MELODIE, 

PICCOLO 

• Blanket manufacturing feasibility 

• Blanket thermal/mechanical/thermo-hydraulic 

performance (small/medium-scale mock-ups). 

• Irradiation and testing of Be-multipliers and solid 

breeders 

• Investigate effect of large and small leaks (H 2 O/LiPb.); 

• corrosion tests. 

MHD experiments and modelling (MEKKA (KIT) • MHD experiments and modeling (HCLL, WCLL: slowvelocity; 

DCLL: high-velocity) 

First wall 

FE-200 (CEA/AREVA), GLADIS (IPP/Ga)/ 

HELOKAKATHELO (KIT), JUDITH 123 (FZJ) 

Breeder T-extraction 

(TRIEX (ENEA) 

MISSION 4: MAJOR R&D AREAS 

Tritium control and extraction from coolants (TLK 

(KIT), HELOKA, + ?) 

• First wall fabrication and qualification (helium-cooled 

and water-cooled) 

• T-extraction technology development (from water and 

helium) 

• T-permeation coatings development incl. irradiation 

(LiPb channels, water, He channels) 


DEMO BLANKET TASKS 2012-2013 

Blanket design development (HCPB, HCLL, and WCLL) 

! Neutronic analyses to determine required breeder thickness to achieve TBR>1. 

! CAD design development of blanket vertical segment 

! Design studies regarding number and size of modules (EM, thermo-hydraulic analyses) 

! Blanket manifold design studies 

! Safety studies (e.g. LiPb-water reaction) to identify basic requirements for blanket design 

! Selected MHD studies prior to DCLL blanket design development 

Blanket feasibility 

! Thermo-hydraulic studies of helium- and water-cooled FW 

! Thermo-hydraulic and thermo-mechanical assessments of modules and manifold 

! Development of preliminary creep-fatigue and ratcheting rules for Eurofer 

Blanket integration 

! Development of blanket attachment: 

Assessment of blanket electromagnetic loads and thermal deformation 

Feasibility assessment of fasteners in irradiated environment 

Study of dynamic amplification of loads on supporting keys 

! Definition of connections of blanket feeding pipes in port 

! Remote handling study to assess in-vessel dynamics 




| PAGE 19 

BLANKET CONCEPTS DESIGN AND 

RELEVANT R&D ISSUES/ACTIVITIES



| PAGE 20 

HCPB BLANKET

HCPB BLANKET: BOX DESIGN 

Loading: Thermal load conditions based 

on a steady state plasma (or pulses >2-8h) 

with a max surface heating of 0.5 MW/m2 

and a max neutron wall load (at the OB 

equatorial blanket) of 2.5 MW/m2. 

Blanket in form of large modules (up to 1 

m x 2 m). This modules are arranged for 

vertical maintenance in a removable 

segment. 

The box containing the breeders is 

designed for low operational pressure 

(about 0.3 MPa) and accidental pressure of 

8 MPa to cope with a possible overpressurisation 

caused by an in-box LOCA. 

The grid provide this feature. 

The Helium in the different structures (FW, 

CAP, Grid and Breeder Units) is supply by 

manifold located in the rear part of the box. 

The manifold structure is enclosed between 

two thick closure plates that are connected 

by stiffening grids. 


HCPB BLANKET: BREEDING ZONE DESIGN 

Breeder Units: Located into the cells 

formed by the grid. U-shaped 

Cooling Plate design. The ceramic 

fills the gap between the 2 Cooling 

Plates, whilst Be fills the remaining 

space of the cell. 

Ceramic Breeder (CB): Li 4 SiO 4 in 

form of pebble bed. Li 2 TiO 3 is an 

alternative candidate. 

Beryllium: Be or Be-alloy pebbles. 

In a ratio of 4:1 respect to the CB. 

Purge flow: a low pressure He flow 

purges the Be and CB pebble beds 

extracting T. The recovery of T from 

He is done outside the VV. 


HCPB BLANKET: R&D NEEDS FOR DEMO 

Computer simulated packing structures in pebble 

beds compared with experiments. The first row 

is the plot from DEM simulation, and the second 

row is from the X-ray tomography experiment. 

Container dia = 48.9 mm, height ~50 mm. 

Sphere particle: 2.3 or 5 mm 

(Y. Gan et al., Thermo-mechanical modelling of 

pebble bed–wall interfaces, Fusion Engineering 

and Design 85 (2010) 24-32) 

Ceramic Breeder Development: To complete 

optimisation and characterisation of Li 4 SiO 4 (by 

melting and spray) and Li 2 TiO 3 (by sintering) to 

DEMO conditions. Irradiation of new produced 

materials. 

Beryllium (as Neutron Multiplier) 

Development: To complete optimisation and 

characterisation of Be pebbles. Irradiation of new 

materials. Safety studies of for the use of 

Beryllium as multiplier in DEMO/FPP and 

definition of related safety requirements (e.g. 

interaction with air and steam at high temperature 

and T retention). Development of Be alloy, if 

requested, to improve performances (e.g. tritium 

retention and steam/water reaction). 

Thermo-mechanics of the Pebble Bed 

(temperature control in pebble beds): To 

complete measurements of bulk/surface thermal 

conductivity in pebble beds and related modeling. 

Modeling development including irradiation 

effects. 

Tritium control: Safety studies on T control in 

DEMO/FPP conditions; definition of safety 

requirement for T control (e.g. requirements in 

term of T permeation reduction factor to the 

steam generator). 


PEBBLE BED TESTING IN HCPB-BU 

CONFIGURATION 

The complexity of the experimental set-up for testing a 

full-scaled breeder unit (BU) mock-up for the European 

Helium Cooled Pebble Bed Test Blanket Module 

(HCPB-TBM) has motivated to build a pre-test mock-up 

experiment (PREMUX) consisting of a slice of the BU in 

the Li 4 SiO 4 region. 

This pre-test aims at verifying the feasibility of the 

methods to be used for the subsequent testing of the 

full-scaled BU mock-up. Key parameters needed for the 

modeling of the breeder material is also to be 

determined by the Hot Wire Method (HWM). 

The modeling tools for the thermo-mechanics of the 

pebble beds and for the mock-up structure are to be 

calibrated and validated as well. 

Francisco Hernández, Matthias Kolb, A. Kunze, A. v.d. Weth , 

Set-up of a pre-test mock-up experiment in preparation for the 

HCPB Breeder unit mock-up experimental campaign, submitted 

to 27 th Symposium on Fusion Technology SOFT (2012). 

PREMUX test section 3D cut. 

Temperature profile at the measurement section: 

heater wires (top) and reference neutronic heating 

(bottom). 




| PAGE 25 

HCLL BLANKET

Main features 

THE HCLL BLANKET DESIGN 

! EUROFER as structural material FW/SW, 

SP and CP cooled by rectangular channels 

! He at 8MPa 

Tinl/Tout = 300/500 °C coolant 

! Pb-Li (Li at 90% in 6Li ) breeder, neutron 

multiplier and tritium carrier 

! PbLi slowly re-circulating (10/50 rec/day) 

LiPb flow 

BUs fed in parallel 

1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. | PAGE 26 

BU 

He Serie flow 

Manifold FW SPs CPs Manifold

BLANKET DESIGN, TRITIUM MANAGEMENT 

2 complementary approaches: 

system analysis and components transfer analysis 

MHD – T transfer diffusion coupling 

between cooling plates 

Tritium concentration profile in PbLi – B = 10 T 

Modelling 

! 1D model study (use of an equivalent mass 

transfer coefficient in the Pb-15.7Li CASTEM 

fluid) 

Results 

! T 2 partial pressure in He ~0.1 Pa ÷ ~0.5E-5 

Pa for rec. rates 1÷100 < limit = 0.55 Pa 

! 30 rec./day proposed compatible with MHD 

pressure drops and corrosion issues 


BLANKET DESIGN: HCLL MHD & CORROSION 

MHD pressure drops 

! Blanket MHD pressure drops estimated at 0.3 MPa for 10 rec./day and B = 10 T 

[Bühler, FED 2005] 

! Assuming Δp ∝ mass flow rate, 30 rec./day ⇒ triple Δp in the blanket. 

! η pump = 0.5 ⇒ P pump = 360 kW, acceptable (He pumping power = 292 MW). 

Corrosion issue 

! Experimental measurements at T = 550°C fitted well by Sannier [1992] correlation for 

martensitic steels up to 480°C ⇒ it can be used for Eurofer at 550°C (to be confirmed 

by experiments) 

! 30 rec./day, radial depth = 775 mm ⇒ v ~ 0.5mms-1 betw. two Cooling Plates, (~9 

mms-1 in the nozzle Stiffening Plates/First Wall) 

! Corrosion rate ~2µm/year bet. 2 CPs; ~29 µm/year in the nozzle; 

! 5 years lifetime: 0.01 mm between two CPs and 0.15 mm in the nozzle, acceptable 

Recommended value of 30 rec./day assumed as reference value 

Many assumptions need to be demonstrated: 

TES efficiency, CPS allowable flow rates and efficiency, steam generator 

achievable PRF, corrosion of Eurofer by Pb-15.7Li.., 


EXP. AND THEORETICAL ANALYSES OF 

MHD FLOWS IN A HCLL BLANKET MODULE 

Experiments 

! pressure drop 

! identification of critical locations for higher 

pressure drop (manifolds, gaps at BP, gaps 

at FW) 

! flow distribution, possibility of flow reversals 

! in uniform and non-uniform magnetic field 

Numerical analyses 

! Electric flow coupling for pressure driven 

MHD flows (4BUs, 24 sub-channels (5 CPs), 

toroidal and poloidal components of 

magnetic field) 

! Buoyancy driven flows with internal heating 

! Analyses of MHD flows in two BUs in nonuniform 

magnetic fields 

! Influence of He-channels (anisotropic electric 

wall conductance) on MHD flows 

L. Bühler, C. Mistrangelo, SOFT-2012 

C. Mistrangelo, L. Bühler, SOFT-2012 

First wall (FW) 

Back plate Draining 

manifold 4 

PbLi exit 

Supplying 

manifold 

PbLi feeding entrance 

( CPs ) Stiffeni 

pol 

Cooling plates 

rad rad 

ng 

tor 

plates 

(SPs) 

B 

Effect of thermal coupling on MHD-buoyant flows in channels 

Effect of nonuniform magnetic fields on MHD Δp 

1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. | PAGE 29 

3 

2 

1

COMPATIBILITY OF STRUCTURAL 

MATERIALS WITH PB-15.7LI 

Corrosion testing of RAFM-steels 

in flowing Pb-15.7Li (HCLL) 

• Corrosion attack is function of temperature and 

flow velocity. 

• Material loss of about 250 and 400 µm/y evaluated 

at flow velocity 0.1 and 0.22 m/s, respectively. 

• Corrosion mechanism is dissolution mainly Fe. 

Modeling tools 

• Development of modeling tools (MATLIM code) 

performed and validated. 

• Calculated values in good agreement with tests. 

Corrosion products 

• Transportation effects of corrosion products and 

the observed precipitation behavior causing loop 

blockage indicate a high risk in TBM operation. 

Further goals: 

• Development of Al based coatings as corrosion / Tpermeation 

barriers 

• Compatibility testing near 1 cm/s range 

Experimental 

value 0.1 m/s 

Short time ~ 

250µm/y 

Testing regimes 

towards TBM’s 




| PAGE 31 

WCLL BLANKET

WATER COOLED LITHIUM LEAD BLANKET 

CONCEPT (1995) 

Main rationales and features 

! Use technology from PWR plants for primary 

circuits 

! Two separate circuits for FW and BZ 

Water Tinl/out = 285/325 °C 

p = 15,5 MPa 

! Removal from the top: Banana concept 

! BZ collectors located at the top of the 

module ⇒ U tubes 

! Double walls and double welds between 

water and LiPb 


WCLL BLANKET CONCEPT FOR DEMO 

ONGOING DESIGN ACTIVITIES 

Segmentation: main modifications 

! Multi module segments removed from the top with 

integrated manifolds and supporting structure 

! BZ collectors located at the rear of the module ⇒ 

C tubes 



ONGOING DESIGN ACTIVITIES 

Design of the blanket module 

! Vertical stiffening plates to reinforce the box against EM 

loads and pressurisation 

! Waved FW to reduce steel thickness (TBR) and max temp 

Total power in the module 4,57 

MW 



DESIGN OF THE OUTBOARD EQUATORIAL 

MODULE 

Blanket modelling, thermal constraint 

! Increased water T inl to cope with Eurofer 

temperature operating window (330 °C - 550°C) 

! To prevent corrosion T_steel/PbLi < 480°C 

! Criteria to prevent subcooled boiling and critical 

heat flux 

T inl = 300 °C 

V inlet = 1.1 m/s 

V outlet = 4 m/s 

302 < T steel < 466 °C 

Detail of the section 

A-A 

Design of the FW – Central 

Module 

316< T < 501 °C 

V = 2.9 m/s 

316< T < 548 °C 


PbLi/WATER INTERACTION: NUMERICAL 

SIMULATIONS 

SIMMER III code 

The SIMMER III code has been chosen as the 

reference code to simulate the experiments. It 

is a two-dimensional, three velocity-fields, 

multi-component, multiphase, Eulerian fluiddynamics 

code coupled with a space and 

energy dependent neutron kinetics model. 

Calculated and experimental pressure trends 

A. Ciampichetti et al. , 2012) 

LIFUS5 computational domain 

1st IAEA DEMO Programme Workshop, UCLA, Antonella 15-18 Oct. Li Puma 2012, | 01 A. Li October Puma 2012 et al. | PAGE 36



| PAGE 37 

DCLL BLANKET

pol. 

rad. 

tor. 

2 He 

sys. 

counter 

flow 

DCLL BLANKET MAIN DESIGN FEATURES 

DCLL outboard blanket 

(cut-out at torus centre) 

E 

P 

P 

Dual-Coolants He/PbLi 

• FW and steel grids are cooled by 8 MPa He 

• Self-cooled Pb17Li acting as breeder and coolant 

Structure 

• Modular blanket design 

• EUROFER as structural material 

• 2-3 mm ODS layer is plated onto the plasma facing FW 

surface, to use high temperature strength of ODS 

Flow channel inserts (FCI) 

• SiC f /SiC FCI for electrical (MHD reduction) and thermal 

insulation (high PbLi exit temp. ≥700°C high thermal 

efficiency of ≥ 40%), no structural functions 

For an early DEMO a version at only ~500°C could be taken 

into account 

PPCS model C: [P. Norajitra et al., Conceptual design of the dualcoolant 

blanket in the frame of the EU power plant conceptual 

study, Fusion Eng. Des., 69 (2003) 669-673.] 

US ARIES-ST studies [Tillack, 1997 and 2003] 1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. | PAGE 38 

Proposed as possible DEMO candidate [Malang, 1994] 

T 

PbLi 

He FCI

THE DUAL COOLANT BLANKET: 

R&D NEEDS FOR DEMO 

! Qualification and specification of SiCf/SiC (electrical, 

thermal, structural, chemical properties). The suitable 

range of electrical and thermal conductivity for the 

SiC-composite are σ = 20–50 1/Ω m, and k=2-5 W/ 

(mK), respectively. [Wong, 2006] 

! Development of fabrication techniques for SiC f /SiC 

inlays. 

! Simulation and testing of 3D flow perturbations due to 

MHD effects in pipe bends and junctions. 

! Prototypical loop featuring magnetic field and heat 

load to study temperature distribution and MHD 

effects in the liquid metal coolant. 

! Study compatibility of heat exchangers with PbLi at 

high temperature. (*) 

! Material selection for liquid metal outlet pipes and 

qualification of connection to Eurofer pipe (e.g. 

welding). (*) 

! Tritium recovery and PbLi purification identification / 

demonstration of acceptable techniques for the PbLi 

temperature level. (*) 

TES: Tritium extraction System 

CPS: Coolant Purification Sys 

CC: chemical control 

(*) reduced requirements in case of a low 

performance DCLL for an early DEMO version 


R&D ON TRITIUM EXTRACTION FROM LIPB 

EFDA 2012: Identification of required technical 

developments to extract T from the liquid metal coolant 

! Aim of the work: to identify the required technical developments to extract tritium from 

PbLi used as blanket breeder and coolant including predictions on costs and durations 

! Review and comparison of candidate technologies (GLC and PAV) ongoing 

Liquid in 

L in , x in 

Liquid out 

L out , x out 

Packed 

Column 

Gas out 

G out , y out 

Gas in 

G in , y in 




| PAGE 41 

COMMON R&D ACTIVITIES

DESIGN CRITERIA GAP ANALYSES 

Divertor and blanket (Water and Helium cooled) description of : 

! The component (function, environment...), 

! The Failure modes considered 

! The Materials 

! The Fabrication processes. 

Three codes analysed: 

! ASME (KIT) 

! RCC-MRx (CEA) 

! SDC-IC rules (CIEMAT) 

Design criteria gap analysis for DEMO 

! Items of interest already covered by code 

! Areas of the code requiring modification or extension to ensure fusion relevance 

! Fusion needs requiring completely new code content 


INVESTIGATION OF HEAT REMOVAL 

IN THE FW (HCLL/HCPB) 

Objectives 

! Manufacturing and testing of a mock-up for experimental investigation of 

heat transfer in the First Wall of HCPB/HCLL TBM/DEMO blankets 

! Development and verification of corresponding CFD Model 

Achieved results 

! Asymmetrical heating of the FW cannot be fully described with standard 1D 

correlations 

! 3D CFD Results with STAR-CD in good agreement with experimental results 

Future work: 

! Investigation on heat transfer enhancing methods 

Comparison between 1D and 2 

D correlations 

M. Ilić et al: Manufacturing and testing of a FW channel mock-up for experimental 

Comparison between calculated 

investigation of heat transfer with He at 80 bars and reference cooling conditions. 

and experimental values 

Comparison with numerical modelling. EFDA TW5-TTBB-001 D10. 


DEMO TRITIUM PERMEATION STUDY 

As a restart of tritium studies for DEMO (major progresses 

in mid 90’s along EU blanket selection exercise) 

Main objectives 

! “identification of candidate working conditions of the different breeding blanket 

concepts from the point of Tritium permeation into the coolant and the identification of 

requirements for the breeding blanket build-up and the coolant purification and Tritium 

extraction system.” 

How to perform 

! Review and state of the art for tritium data in materials, including permeation barriers 

! Review and state of the art for tritium processes in He, PbLi, water 

! Evaluate with the same simulation tool based on simplified model 

“FUS-TPC” 3 different blanket concepts (HCLL, HCPB, WCLL) 


SUMMARY (1/2) 

EU DEMO timeplan 

! Pre-conceptual design (2011-14) ⇐ PPPT 

! Construction (2030-40) 

! Two phases: exchangeable blankets (same coolant), increasing dpa 

EU strategy and programme 

! High component reliability will be a main design driver for DEMO Simplified designs, 

established technology, qualified materials also for BoP components 

! Selection of breeding blanket concepts to be adopted for DEMO phase 1 now is 

premature. Still uncertainties/ technical risks. 

! EU reference blanket concepts (HCLL and HCPB) further investigated to be adapted to 

DEMO phase 1 requirements and specification 

! WCLL concept developed to conceptual level as a back up solution 

! Reduced performances DCLL investigated to conceptual level 

! A down selection to one concept should be made ~2020 for the DEMO EDA phase 


SUMMARY (2/2) 

Present breeding blanket R&D activities and prospects 

! HCLL, HCPB, WCLL blankets design according to phase 1 DEMO requirements 

! Tritium management (component and cycle level) for the four assessed concepts 

! Design code for in vessel components design ‘existing code 

! MHD and material compatibility on liquid breeder blanket concepts 

An extensive R&D programme needs to be launched to 

investigate main issues of various concepts in order to 

allow a selection based on technical rationales 

! Manufacturing 

! MHD and material compatibility on liquid breeder blanket concepts 

! Tritium technology 

! Coolant technology 

! … 


SOME REFERENCES 

! A. Aiello et al., Mock-up testing facilities and qualification strategy for EU ITER TBMs, FED 85 (2010) 2012–2021 

! G. Aiello et al., Thermal–hydraulic analysis of the HCLL DEMO blanket, FED 82 (2007) 2189–2194 

! G. Aiello et al., Transient thermo-hydraulical/thermo-mechanical analysis of the HCLL-TBM for ITER, FED 85, Issues 7–9, 2010, 1565-1572. 

! G. Aiello (CEA) and al., HCLL TBM design status and development, FED 86 (2011) 2129. 

! Francisco Hernández et al., Thermo-mechanical analyses and assessment with respect the design codes and standards of the HCPB Breeder Unit, Fusion Engineering and Design 87 (2012) 1111– 1117. 

! L.V. Boccaccini et al., Present status of the conceptual design of the EU test blanket systems, FED 86 (2011) 478-483. 

! A. Ciampichetti, I. Ricapito, N. Forgione, A. Pesetti, Pb-16Li/water interaction: experimental results and preliminary modelling activities, presented at Symposium On Fusion Technology (SOFT-2012), September 24-28, 

2012 Liege (Belgium) 

! F. Cismondi (KIT) et al., HCPB TBM thermo mechanical design: assessment with respect codes and standards and DEMO relevancy, FED 86 (2011) 2228. 

! W. Farabolini, Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor, FED Volume 81, Issues 1–7, 2006, 753-762 

! F. Gabriel et al., A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket module, FED 82 (2007) 2204–2211 

! O. Gastaldi et al., Tritium transfers and main operating parameters impact for demo lithium lead breeding blanket (HCLL) , FED 83, Issues 7–9, 2008, 1340-1347 

! R. Kemp, DEMO design summary, March 2012 ,EFDA_D_2L2F7V 

! A. Li Puma et al., Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant, FED Volume 81, Issues 1–7, 2006, 469-476 

! A Li Puma et al., Requirements and proposals for control and monitoring measurements of the HCLL TBM, FED Volume 85, Issues 7–9, 2010, Pages 1642-1652 

! A. Li Puma et al., Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor, FED Volume 84, Issues 7–11, 2009, Pages 1197-1205. 

! E. Magnani et al., DEMO relevance of the test blanket modules in ITER—Application to the European test blanket modules, FED, 85, Issues 7–9, 2010, Pages 1271-1278. 

! P. Norajitra, L. Bühler, U. Fischer, S. Gordeev, S. Malang and G. Reimann, Conceptual design of the dual-coolant blanket in the frame of the EU power plant conceptual study, FED., 69 (2003) 669-673. 

! P. Sardain, Power plant conceptual study—WCLL concept, FED Volume 69, Issues 1–4, September 2003, Pages 769-774 

! P. Sardain, The European power plant conceptual study: Helium-cooled lithium–lead reactor concept , FED Volume 81, Issues 23–24, November 2006, Pages 2673-2678 

! Xue Zhou Jin, Brad Merrill, Lorenzo Virgilio Boccaccini, Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system, FED in print. 


| PAGE 49 



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| PAGE 50 

SPARE SLIDES

DTT 

Shortlist 

Design 

Materials (M3) 

Review PIE 

Pilot IFMIF 

30 dpa testing 

50 dpa testing 

Input to C&S 

ITER DT 

Q=10 long pulse 

R&D on DEMO BB 

Results ITER TBM 

DEMO 

CDA* 

Divertor concept 

EDA 

C&S available 

FDR 

DEMO Timeline 

w. Interlinks to other Projects 

12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 

* Concept variants evaluation, concept design, concept selection 

1st IAEA DEMO Programme Workshop, 

UCLA, 15-‐18 Oct. 2012, A. Li Puma et al. 

Construc=on 

51

DEMO DEVELOPMENT TIME PLAN 

! Pre-conceptual design (2011-14) ⇐ PPPT 

! Design and R&D – CDA (2014-20) 

! Design and R&D – EDA (2020-30) 

! Construction (2030-40) 

• Plant Requirements Document (Overall Mission and Requirements) 

• Operational Concept Description (Incl. Physics basis and Operational Scenario) 

• System Requirements Documents (SRD) (for each major plant system/ Identification of Interfaces between systems 

• System Design Description Documents (Report describing the concept design rationale for each system incl. material specs 

• System Integration (3D CAD model of Plant) 

• Preliminary Safety Report 

• Plant RAMI Report (Preliminary Failure Modes, Effects and Criticality Analysis Report/ Maintainability / Inspection Analysis) 

• Preliminary Manufacturing Plan 

• Preliminary Assembly & Maintenance Plan/ Test & Commissioning Plan/Decommissioning & Disposal Plan 

• Programme Management Plan (for EDA phase) (R&D Plan/ Manpower / Skills requirements/ Programme Risk Analysis) 


PPCS AND DEMO BLANKET OPTIONS 

! Many remaining challenging issues to be resolved for the 

development of the DEMO blanket. 

! T-self-sufficiency: a complex issue that depends on many 

system physics and technology parameters / conditions. 

! Choices of breeding blanket materials and coolant to be 

made consistently with the choice of the Balance of 

Plant (BoP). 

Coolant Breeder/ 

Multiplier 

Structural 

Materials 

Coolant T in / T out 

Comment 

HCPB He Li 4 SiO 4 /Be Eurofer ~300/500 o C # ITER TBM 

HCLL He LiPB Eurofer ~300/500 o C # ITER TBM 

WCLL Water LiPb Eurofer 290 / 325 o C PWR conditions 

DCLL He (FW), LiPb (BB) LiPb Eurofer ~300/500 o C # DEMO TBM 

Vacuum Vessel: 316 SS water self-cooled; # Eurofer limit 


HCPB BLANKET: BU DESIGN ANALYSES 

! Objectives: Optimisation of the design . A first run of thermo-mechanical analyses and assessment with the design codes and 

standards (RCC-MR + SDC-IC) showed that in several section M-type damage criteria ware not fulfilled. 

! Results: After some detailed design iterations, the base geometry of the BU was modified until all the design criteria were 

fulfilled. 

Francisco Hernández et al., FED 2012. 


MECHANICS OF BINARY AND 

POLY-DISPERSE PEBBLE ASSEMBLY 

Mono-size, binary and poly-disperse pebble 

assemblies are studied under uni-axial compression 

Mono size assemblies show stiffer response 

compared to binary and poly-disperse assemblies 

The large pebbles take most load while small 

pebbles move around large pebbles making the 

overall system compliant 

The residual strain after unloading in binary and 

poly-disperse assemblies is large compared to 

mono-size assemblies 

In a poly-disperse packing, small pebbles between 

large pebbles shows a ball bearing like effect 

R. K. Annabattula, Y. Gan and M. Kamlah, Fusion Engineering and Design, 2012 


MODEL C: MODULAR DESIGN WITH PERMANENT 

AND EXCHANGEABLE PARTS 

coolant 

manifolds (d) 

(permanent) 

cold shield 

30 cm (c) 

(permanent) 

8 

9 

7 

6 

10 11 

5 

4 

3 

2 

1 

48 divertor plates (b) 

(1-2 yrs. lifetime) 

b 

c 

a 

e 

d 

h 

f 

g 

16 TF coils 

8 upper ports (f) 

(modules & 

coolant) 

176 blanket 

modules (a) 

(5-6 yrs. lifetime) 

8 central ports (g) 

(modules) 

vacuum vessel 

70 cm (e) 

(permanent) 

lower divertor ports (h) 

(8 remote handling, 16 coolant) 


MODEL C: THE RADIAL BUILD 

IB/OB blanket thickness (incl. shield): 1.1/1.6 (m) 

Component Radial build (m) 

TF coil 1.84 - 3.34 

Vessel and gap 3.34 - 3.76 

Shield / blanket / first wall 

(IB) 

3.76 - 4.86 

Plasma 5.01 - 10.03 

Shield / blanket / first wall 

(OB) 

10.18 - 11.78 

Vessel + gap 11.78 - 12.93 

TF coil 12.93 - 15.65 

1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. 

57

Operating 

parameters 

PbLi/WATER INTERACTION: PAST 

EXPERIMENTS 

Test n.3 Test n.4 Test n.5 

Pb16Li temperature 330 °C 330 °C 330 °C 

Water injection 

pressure 

155 bar 155 bar 150 bar 

Water temperature 295 °C 325 °C 265 °C 

Sub-cooling 50 °C 20 °C 77 °C 

Free volume in S5 5 l 5 l 4 l 

Water injector 

penetration in S1 

Time of water 

injection (V14 open) 

Operating 

parameters 

160 mm 160 mm 160 mm 

6 s 6 s 12 s 

Test n.6 Test n.7 Test n.8 

Pb16Li temperature 330 °C 330 °C 430 °C 

Water injection 

pressure 

160 bar 160 bar 160 bar 

Water temperature 320 °C 320 °C 320 °C 

Sub-cooling 27 °C 27 °C 27 °C 

Free volume in S5 10 l 10 l 10 l 

Free volume in S1 7.5 l 7.5 l 7.5 l 

Water injector 

penetration in S1 80 mm 80 mm 80 mm 

Time of water 

injection (V14 open) 12 s 12 s 12 s 

Operating 

conditions 

LIFUS 5 Facility 

Experimental results 

1st IAEA DEMO Programme Workshop, UCLA, 15-18 Oct. 2012, A. Li Puma et al. 

| PAGE 58

T TRANSPORT ANALYSIS BY FUS-TPC 

F. Franza et al. HCPB with FUS-TPC (SOFT 2012) 


Deposited Al 

DEVELOPMENT OF AL BASED COATINGS AS 

CORROSION / T-PERMEATION BARRIERS 

ECA process – Development of Al coating from toluene based electrolyte 

Step 1: Development of heat treatment process to optimize microstructure of galvanized Eurofer 97 

Step 2: Compatibility tests in Pb-15.7Li are in progress 

Step 3: Permeation tests gas / Pb-15.7Li to be initiated 

ECX process – Improved process for Al coating from electrolytes based on ionic liquids 

Coating and electrolyte 

Al layer 

Matrix 

Resin 

• New ECX process is reproducible 

• Scale thickness controllable by current + time 

• Al scale on front and back side similar 

• Industrial relevance 


SEM ANALYSES OF PB-15.7LI EXPOSED 

AL COATED EUROFER 

α-‐Fe(Al) 

Eurofer 

E-‐F-‐1 20 µm annealed, Kirkendall before pores 

Eurofer steel 

α-‐Fe(Al) 

Line scan 

Pb-‐15.7Li 

FeAl 

…and aIer 5298 h at 550°C in PbLi 

Al 2 O 3 

No visible corrosion attack 

of ECA processed Eurofer 

In flowing Pb-15.7Li 


Precipitations in cooler loop sections due to 

dissolution of Fe, Cr in the hot section 

Pb-17Li 

DISSOLUTION/PRECIPITATION IN 

DYNAMIC PB-15.7LI 

Fe-Cr-Mn precipitates 

Precipitations near tube walls 

Schematic view of loop position 

AC = Air cooler 

MT = Magnetic trap 

Precipitations in the centre of the 

magnetic trap parallel to field lines 

Precipitations in adherent Pb-17Li 

scale 

Amount of precipitates 

typically: 

4 kg Fe/m 2 ⋅year 


ANALYSIS OF FE-‐CR PRECIPITATES FORMED IN PB-‐15.7LI 

DURING NEW TEST CAMPAIGN AT 550°C IN PICOLO LOOP 

Adherent Pb-15.7Li layer at the 

inner wall of a drained tube 

Adherent Pb-15.7Li layer at the inner 

wall of the heater with precipitates 

No coating of tube wall in 

cold section 

12.5 µm 

Channel of EM-pump 

Accumulated/‘grown’ corrosion 

products mixed with Pb-15.7Li 

amount in a duct with magnetic 

field leading to blockage 

Large precipitates embedded 

in Pb-15.7Li near inlet MT 

Control of Pb-15.7Li chemistry is of great importance for TBM operation

Li Puma - Advanced Projects Homepage

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