Solid Breeder Blanket R&D and Deliverable

TBM Costing Kickoff Meeting

INL, August 10-12, 2005

Presented by

Alice Ying

Mission statement of HCCB TBM

To utilize ITER testing capability to provide critical experimental data to the development of:

1) a breeding technology for producing the tritium necessary for the continued DT fusion research and the extended operation of ITER, and

2) a blanket technology for the extraction of high grade heat and electricity production

Mission statement of HCCB R&D

Perform “valued research” to gain access to the larger international R&D program (EU and JA) and deliver the 1st test article

Blanket R&D and Manufacturing Schedule for ITERID ID Task Name

1 1 ILE establishment2 2 VV call for tender3 3 VV contract award4 4 T=0 Regulatory approval5 5 Start of excavation at site & building construction6 6 Start of VV material procurement7 7 Start of VV fabrication8 8 First sets ov VV sectors, TF coils and VVTS delivered on site9 9 Start of tokamak assembly10 10 Completion of VV torus and start of in-vessel components installation11 11 Complete & close cryostat12 12 First plasma (Dec 2015)13 13

14 14 Blanket15 15 Detailed design16 16 Development of blanket TSD (Technical specification document)17 17 Development of FW qualification criteria18 18 Blanket R&D19 19 Base blanket R&D20 20 Fabrication of mock-ups for qualification and verification tests21 21 Prototype fabrication and tests22 22 ITER FW/blanket manufacturing23 23 FW/blanket call for tender24 24 FW/blanket contract award25 25 FW/blanket manufacturing design26 26 FW/blanket material procurement27 27 FW/blanket fabrication and tests28 28 FW/blanket delivery to the ITER site

27/02/2006 ILE establishment

17/07/2006

05/02/2007 VV contract award

07/01/2008 T=0 Regulatory approval

04/02/2008 Start of excavation at site & building construction

07/01/2008 Start of VV material procurement

07/07/2008 Start of VV fabrication

03/10/2011 First sets ov VV sectors, TF coils and VVTS delivered on site

07/11/2011 Start of tokamak assembly

Completion of VV torus and start of in-vessel components installation 07/04/2014

13/10/2014

28/12/2015

14/07/2008

05/01/2009

'03 '04 '05 '06 '07 '08 '09 '10 '11 '12 '13 '14 '152003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015

Key elements of ITER shielding blanket WBS1. Detailed design2. Development of blanket TSD3. Development of FW qualification criteria4. Blanket R&D 5. ITER FW/blanket manufacturing

R&D program on HCCB DEMO & TBM (Typical)

Structural material development and characterizationFabrication technologies (structural material) Ceramic breeder and Be multiplier pebbles (or other suitable forms) development and characterization (fabrication and procurement)Pebble bed characterization Tritium control and extraction technologiesTritium cycle modelingAncillary systems development (He cooling technology) Instrumentation developmentTBM mockup tests QA/Qualification Criteria, TSDTBM fabrication and qualification prior to installation

Current US R&D (except structural material development) is mainly carried out by the graduate students (four at UCLA)

Several R&D projects were initiated, however they were discontinued and/or not pursued in depth because of the continued program changes

The ITER TBM program provides a driving force to bring Fusion Nuclear Technology “R&D” the first step toward reality

Indeed, a large R&D program exists in both EU and JA

• Can we access it freely?• Is the data available universally?

Effective thermal conductivity of Be pebble bed vs. temperature

Processes toward ITER TBM Database Preparation (on breeding elements)

As a part of IEA collaboration

Data Collection

Data Assessment ITER TBM MDB

Unified Procedures(TBD via IEA

collaboration?)

Recommendations

Quantification of uncertainty

Acceptance of data

What data needed?

What experimental conditions?

(1st Cut)

EM/S NT

Ceramic breeder and Be neutron multiplier:pebble development and characterization

• Procurement and quality control of lithium ceramic breeder pebbles (Li4SiO4, Li2TiO3) and Be pebbles

• pebble size and shape, low impurity content, mechanical properties, density, microstructure, process reproducibility, production optimization and engineering scaling

• Recycling processes for Li, Be

• Ceramic breeder and Be pebbles behavior under irradiation (mechanical properties, T release)

• Modeling of radiation damage, T kinetics and thermal creep in irradiated Be and of helium and tritium behavior in Be

• Improved Be and Be alloys material development (enhanced T release, limited He embrittlement, limited reaction in air)

glassy

Cost, Risk and Benefit

Material TBM Action Costing Action

Ferritic Steel

to call for tender (can either be a US or an oversea company)

Zinkle to estimate cost based on conceptual design drawings (need to include numbers of coolant channels, etc.)

Ceramic breeder pebble

a. to purchase from CTI/CEA (Li2TiO3 pebbles)

b. to purchase from FZK (Li4SiO4 pebbles)

c. initiate a collaborative development program with KO or China

Ying to check purchase price from CTI

Beryllium pebble

To purchase from NGK Ying to check purchase price from NGK

Material Fabrication/Procurement

One possible risk: Role of the US on ITER breeding blanket development

Scopes of Characterization on Breeding Elements Thermomechanics

1. Pebble materials

• Thermo-physical properties, mechanical properties, tritium release characteristics, irradiation effects, etc.

2. Pebble bed unit

• Effective thermo-physical properties, effective thermo-mechanical properties, irradiation effects, etc.

3. Breeder unit (with structure)

• Stress-strain magnitudes under blanket operating conditions, temperature profiles, deformation profiles, cyclic effects, etc.

Three main categories:

Uni-axial compression tests have been performed to generate data base of effective modulus and pebble bed

creep deformation rate for Li4SiO4 pebble beds

Creep strain as a function of creep time

CFD analysis and laboratory experiments are needed to verify helium manifold design

• Multiple parallel paths per flow distributor

• Multiple parallel channels per flow path

• The goal is to ensure that helium flow is properly distributed

EM/S and NT Unit Cells

Tritium permeation: Uncertainties in the database

• Permeability / Solubility data and Pressure effect

0.001

0.002

0.003

0.004

0.005

0.006

0.007

0.008

0.009

650 700 750 800 850

F82 H [100 Pa< P< 1000 Pa]

F82H [105 Pa]

Eurofer

Temperature (K)

• At higher pressure, the permeation regime appears to be diffusion limited or J~ P0.5, i. e. permeability is governed mainly by hydrogen transport through the bulk. At the lower temperatures and lower pressures (773 K or lower), the pressure dependence of J is somewhat steeper in the low-pressure or J~ P0.63. This can be explained by a more pronounced surface influence on the permeability.

• Note that the tritium partial pressure is < 10 Pa in the purge.

References:

E. Serra, A. Perujo, G. Benamati, “Influence of Traps on the Deuterium Behavior in the Low Activation Martensitic Steels F82H and Batman,” J. Nucl. Mater, 245 (1997) 108-114.

A. Pisarev, V. Shestakov, S. Kulsartov, A. Vaitonene, “Surface Effects in Diffusion Measurements: Deuterium Permeation through Martensitic Steel,” Phys. Scr, T94 (2001) 121.

D. Levchuk, F. Koch, H. Maier, H. Bolt, “Deuterium Permeation through Eurofer & A-alumina Coated Eurofer,” J. Nucl. Matet, 328 (2004)103-106

Summary Table Without H2 With 100 wppm H2

Purge gas velocity

J3/J1 PHT at the 1 m

downstream

J3/J1 PHT at the 1 m

downstream

T= 673 KEurofer

0.01 m/s 5.62% 4.23 Pa 0.80% 4.46 Pa

0.03 m/s 3.3% 1.50 0.271% 1.56

0.05 m/s 2.55% 0.92

0.1 m/s 1.8% 0.47

F82 H 0.03 m/s 0.56% 1.55

T= 773 KEurofer

0.01 m/s 13.81% 4.33 2.21% 4.95

0.03 m/s 8.18% 1.63 0.716% 1.77

0.05 m/s 6.36% 1.01 0.417% 1.08

0.1 m/s 4.49% 0.52

F82H 0.05 m/s 0.88% 1.07

Calculated permeation rate appears high and unacceptable without taking into account isotope swamping effects or using permeation reduction barriers.

Cost Estimates for Unit Cell and SubmoduleParameters Unit Cell Submodule (TM)

Size, m3 0.1925 x 0.211 X 0.6 0.73 x 0.91 x 0.6

Total breeding volume (0.4 m) 0.016247 0.26572

Number of units 3 1

Breeder volume per unit, m3 0.00633 0.0702

Beryllium volume, m3 0.0066314 0.10399

Total ferritic steel volume, m3 0.020089 0.147

Total breeder weight, kg 3.45 x 0.9 x 0.6 x 0.00633 x3=35.37 3.45 x 0.9 x 0.6 x 0.0702= 131 kg

Total beryllium weight, kg 1.85 x 0.6 x 0.0066314 x 3 =22 1.85x0.6 x 0.104 =115.4 kg

Total ferritic steel weight, kg 154.6 x 3= 464 kg 1132 kg

Breeder cost 1 $ 350K x0.7 = $ 245K $ 1.3 millions x 0.5 = $ 650 K

Beryllium cost2 $ 198K x 0.7 = $ 145K $ 1. millions x 0.5 = $ 500 K

Breeder + Beryllium cost $ 390 K $ 1150 K

Total estimated cost 0.6 millions 2.0 millions

Li2TiO3 Li4SiO4 Be Ferritic Steel

TD 3.45 2.4 1.85 7.7

Fabricated density 90% 98% 100% 100%

Cost /kg $ 10K1 $ 10K $ 9K2

1. CEA price if purchasing 1 kg. Cost analysis assumes 30% discount if purchase in tenth kg amount, and 50% discount if hundreds of kg.

2. NGK beryllium pebble price. Same discount applied to beryllium cost.

Summary

• If agreed upon by major responsible parties, the US as a support role can reduce a significant amount of financial burden, yet obtain critical data for breeding blanket and electricity generation technology development

• Nevertheless, the US “TBM” should be ready for integration into (e.g. EU) Port Module in 2013 to be inserted into ITER (2014)

• Focus on “valued research” (enhanced predictive capability and safety feature) to gain access to a larger data base – Breeder unit thermomechanics – Tritium control and permeation

• Additional cost items (US’ contribution: x%)– Port Frame, Port Plug– Helium Loop and associated piping system – Port Cell Coolant Conditioning Components – Tritium Extraction System– Tritium Measurement System– Special Remote Handling Tools– Hot Cell and PIE– Waste disposal