Solid Breeder Blanket R

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Solid Breeder Blanket R

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1) a breeding technology for producing the tritium necessary for the continued ... Behavior in the Low Activation Martensitic Steels F82H and Batman,' J. Nucl. ... – PowerPoint PPT presentation

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Title: Solid Breeder Blanket R


1
Solid Breeder Blanket RD and Deliverable
Presented by Alice Ying
  • TBM Costing Kickoff Meeting
  • INL, August 10-12, 2005

2
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 RD Perform valued
research to gain access to the larger
international RD program (EU and JA) and deliver
the 1st test article
3
Blanket RD and Manufacturing Schedule for ITER
4
RD program on HCCB DEMO TBM (Typical)
  • Structural material development and
    characterization
  • Fabrication 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 technologies
  • Tritium cycle modeling
  • Ancillary systems development (He cooling
    technology)
  • Instrumentation development
  • TBM mockup tests
  • QA/Qualification Criteria, TSD
  • TBM fabrication and qualification prior to
    installation
  • Current US RD (except structural material
    development) is mainly carried out by the
    graduate students (four at UCLA)
  • Several RD 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 RD the first
    step toward reality

5
Indeed, a large RD 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
6
Processes toward ITER TBM Database Preparation
(on breeding elements) As a part of IEA
collaboration
7
(1st Cut)
EM/S
8
Ceramic breeder and Be neutron multiplierpebble
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)

9
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10
Cost, Risk and Benefit
Material Fabrication/Procurement
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 to purchase from CTI/CEA (Li2TiO3 pebbles) to purchase from FZK (Li4SiO4 pebbles) 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
One possible risk Role of the US on ITER
breeding blanket development
11
Scopes of Characterization on Breeding Elements
Thermomechanics
12
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
13
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
14
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15
Tritium permeation Uncertainties in the database
  • Permeability / Solubility data and Pressure
    effect
  • 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 lt 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
16
Summary Table
Without H2 Without H2 With 100 wppm 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 K Eurofer 0.01 m/s 5.62 4.23 Pa 0.80 4.46 Pa
T 673 K Eurofer 0.03 m/s 3.3 1.50 0.271 1.56
T 673 K Eurofer 0.05 m/s 2.55 0.92
T 673 K Eurofer 0.1 m/s 1.8 0.47
F82 H 0.03 m/s 0.56 1.55
T 773 K Eurofer 0.01 m/s 13.81 4.33 2.21 4.95
T 773 K Eurofer 0.03 m/s 8.18 1.63 0.716 1.77
T 773 K Eurofer 0.05 m/s 6.36 1.01 0.417 1.08
T 773 K Eurofer 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.

17
Cost Estimates for Unit Cell and Submodule
Parameters 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 x335.37 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.
18
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
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