Preliminary Design of China ITER TBM

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• Preliminary Design of China ITER TBM
• with Helium-Cooled and Solid Breeder Concept

Presented By K.M. Feng (On behalf of CH HCSB
TBM Team) Presented at 3rd PRC/US MCF
Collaboration workshop Dalian, China, May
18-19, 2006 1
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Outline

1. Introduction
2. Design Progress
3. Performance Analysis
4. RD and Test Plans
5. Possible Collaborations
6. Summary

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I. Introduction

• ITER will pay a very important role in first
  integrated blanket testing in fusion environment.
  Some DEMO blanket relevant technologies, such as
  tritium-breeding self-sufficiency, exaction of
  high-grade heat, safety requirement, and design
  criteria will be demonstrated in ITER test
  blanket modules (TBMs).
• China planed to develop independently own TBM
  for testing during ITER operation period based on
  Chinas DEMO definition and development strategy.
  
• The preliminary design and analysis of HC-SB TBM
  have been carried out recently. Possible
  collaborations on TBM RD with other partiers
  have been proposed.

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ITER,TBM and DEMO
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Definition of DEMO in China

• The DEMO in China is to demonstrate the safety,
  reliability and environment feasibility of the
  fusion power plants, meanwhile to demonstrate the
  prospective economic feasibility of the
  commercial fusion power plants.
• Utilization of fusion energy have still a long
  way to go towards an economically commercial
  power plant. DEMO in China should be an
  indispensable step prior to the commercial
  application.
• In addition, China is interested in non-electric
  applications of fusion energy, such as HLW
  disposal and hydrogen production, etc. we expect
  that these applications will benefit the ultimate
  development of the fusion power plants.

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Selection of DEMO Blanket

• Two options of breeding blanket with ceramic and
  lead lithium-lead breeders might be chosen as
  Chinas DEMO blanket concepts under the
  conditions of meeting the requirement of the
  neutronics, thermo-hydraulics and mechanics
  aspects.

HC-SB DEMO Blanket(SWIP) DCLL
DEMO Blanket(ASIPP)
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Selected HCSB DEMO Parameters
Chinese HC-SB Demo Parameters
Fusion power/electric power (MW) 2000 / 600MWe
Major radius (m) 7.0m
Minor radius (m) 2.5m
Neutron wall load (MW/m2) 2.0
Surface heating (MW/m2) 0.3
Tritium breeding ratio (TBR) gt1.1
Availability () 50-70
Divertor peak load (MW.a/m2) 8.0 (water-cooled)
Plasma operation mode Continuous
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HC-SB DEMO Blanket Design
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II. Design progress of CH HC-SB EM-TBM
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HC-SB TBM
HC-SB EM-TBM (I) HC-SB EM-TBM (II)
HCS
Port C
630mm(d) X 660mm(w) X 890mm(h)
TWCS

It is in agreement with other partiess design,
HC-SB TBM design is based on a vertical half-port
space in test Port C
Test Port Space for CH HC-SB TBM
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Originally Design of CH HC-SB TBM (2004 Version)
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1-beryllium armor, 2-multiplier zone, 3-sidewall,
4-U-shaped shell, 5-cooling pipes, 6-breeder
zone, 7-backplane, 8-He coolant(hot leg),
9-measure access, 10-attachment, 11-purged, 12-He
coolant (cold leg)
Be
Solid Breeder
Back-plane
He
He
Outline view for CH originally HC-SB TBM design
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Exploded 3-D view of Modified Design of HC-SB TBM
(2005 Version)

Structure and components design in detail is on
going.
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Structure Design for EM-TBN
Be armor 2 mm Max Temp. 514OC First
wall thickness 30 mm Material Eurofer
Max T 506OC Cooling tube
18x14.5mm Unit cells 3X3 sub-modules He
pressure 8 MPa
630mm
664mm
664mm
890mm
Sub-modules
0.190 m in toroidal 0.420 m in radial 0.260 m
in poloidal
Integration view of structure design
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Schematic view of CH HC-SB EM-TBM
Cross-section of module
Outside of structure
Coolant manifold
Sub-module structure
View of the back-plane
Configuration of Sub-modules
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Connection of Up-down Modules
Connection
HC Pipe (outlet)
Up module
HC Pipe (inlet)
Down module

• Modularizing structure
• Parallel connecting two modules

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Connection of Components
FW attachment
TBM in ITER frame
Flow path of coolant
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Structure View of Back-plane
Purge Collection manifold
Purge Supply manifold
Arrangement of back-plane
The back-plane closes the sub-module box from the
near side, provides the support for the
mechanical attachment at the interface with the
ITER Port Plug and forms a manifold system for
others part of TBM
Top view of manifold
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Assembly of HC-SB EM-TBM in frame
TBM module
Frame
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HCSB TBM integrated assembly
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Design parameters for the HC-SB TBM
Items NT-TBM EM-TBM
Configuration BOT (Breeder Out of Tube) Modules 33 Sub-modules Modules 33 Sub-modules
First wall area Neutron wall loading Surface heat flux 0.664 m(W)0.890 m(H) 0.591 m2. 0.78 MW/m2 0.3 MW/m2 (normal condition) 0.5 MW/m2 (extreme condition) 0.591 m2 0.591 m2 (Vertical). 0 0.1 MW/m2 (normal condition) 0.3 MW/m2 (extreme condition)
Total heat deposition surface heat flux included 0.76 MW 0.177 MW
Globe TBR Lithium orthosilicate, Li4SiO4 1.15 (1-D), 80 Li-6
Tritium production rate ITER operation condition 2.23 10-2 g/d
Sub-module dimension (P) (T) (R) 260 mm190 mm420 mm 260 mm190 mm420 mm
Ceramic breeder (Li4SiO4) Two size Thickness Max. Temperature Diameter 0.51 mm, pebble bed 90 mm (four zones) 737 ? SiC pebble bed, 0.51 mm
Neutron multiplier (Beryllium) Two size Thickness Max. Temperature Diameter 0.51 mm, Pebble bed 200 mm(five zones) 617 ? Al pebble bed, 0.51 mm
Be armor Thickness Max. Temperature 2mm 543 ? 2mm 514 ?
Structure Material Ferritic steel Max. Temperature EUROFER 530 ? EUROFER 506 ?
Coolant helium (He) Pipes size Pressure Pressure drop Temperature range (inlet/outlet) Mass flow Diameter (OD/ID) 8 Mpa 0.294 MPa 300/500 ? 0.73 kg/s 85/80 mm 8 Mpa 0.051 MPa 300/411 ? 0.31 kg/s 85/80 mm
He purge flow (He) Pressure Pressure drop 0.12 MPa 0.02 MPa
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Schematic views of Coolant flow
Coolant flow in the sub-module
Coolant flow in FW
Coolant Flow Direction
Back-plate
Back-plate
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HC-SB TBM Auxiliary System
VV
Port Cell
TWCS vault
HC-SB TBM
HCS
CPS
BC
TMS
Tritium Building
NMS
TES
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HC-SB TBM Auxiliary Sub-system Design
HCS
TMS
TES
TCWS
CPS
NMS
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Neutronics Measurement System Design
micro-fission chamber
Schematic diagram of neutron fluxes and spectra
measurement system and cooling loop for NT-TBM
micro-fission chamber assembly
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Iii. Performance Analysis for EM-TBM
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A. Neutronics design B. Thermo-hydraulic
Analysis C. Thermo-Mechanical Analysis
D. Preliminary E-M analysis E. Preliminary
LOCA, LOFA analysis, etc.,Above performance
analysis have been completed. Others calculation
and performances analyses are on going.Related
results have been given in the CH HC-SB TBM DDD
report last year.
Preliminary Performance Analysis for EM-TBM
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Performance Analysis for HC-SB TBM (Cont)
Calculation Model
Temperature distribution
The displacement vector sum
Peak stress is 63.5 MPa
Flow scheme
Temperature on Flow Channel
The stress distribution
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Main Design Parameters of HC-SB EM-TBM1
Components Normal condition Normal condition Extreme condition Extreme condition
Components EM-TBM NT-TBM EM-TBM NT-TBM
Neutron surface loading MW/m2 0 0.78 0 0.78
Surface heat flux MW/m2 0.1 0.3 0.3 0.5
Helium pressure MPa 8 8 8 8
Helium inlet/outlet temperature C 300/411 300/500 300/411 300/500
Total power (surface heat flux included) MW 0.059 0.64 0.177 0.76
Power from surface heat flux MW 0.059 0.18 0.177 0.30
Power from nuclear heating MW 0 0.46 0 0.46
Total Mass flow rate of helium kg/s 0.10 0.62 0.31 0.73
Mass flow rate of helium in
FW kg/s 0.10 0.62 0.31 0.73
Single sub-module kg/s 0.011 0.065 0.032 0.077
Top and bottom plates kg/s 0.0057 0.03 0.017 0.04
Velocity of helium in
FW m/s 9.0 58 27 69
Sub-module m/s 2.4 15 7.2 18
Pressure drop of coolant in module MPa 0.0066 0.21 0.051 0.29
Pressure drop in FW MPa 0.0059 0.19 0.045 0.26
Pressure drop in sub-module MPa 0.00068 0.02 0.0052 0.03
1.Temperature at FW outlet is fixed at 4110C
for test of high temperature performance of FW.
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Main Design Parameters of HC-SB EM-TBM
(cont)2
Components Normal condition Normal condition Extreme condition Extreme condition
Components EM-TBM NT-TBM EM-TBM NT-TBM
EM-TBM NT-TBM EM-TBM NT-TBM
Neutron surface loading MW/m2 0 0.78 0 0.78
Surface heat flux MW/m2 0.1 0.3 0.3 0.5
Helium pressure MPa 8 8 8 8
Helium inlet/outlet temperature C 300/313.4 300/500 300/341 300/500
Total power (surface heat flux included) MW 0.059 0.64 0.177 0.76
Power from surface heat flux MW 0.059 0.18 0.177 0.30
Power from nuclear heating MW 0 0.46 0 0.46
Total Mass flow rate of helium kg/s 0.85 0.62 0.83 0.73
Mass flow rate of helium in
FW kg/s 0.85 0.62 0.83 0.73
Single sub-module kg/s 0.089 0.065 0.087 0.077
Top and bottom plates kg/s 0.047 0.03 0.046 0.04
Velocity of helium in
FW m/s 69 58 69 69
Sub-module m/s 18 15 18 18
Pressure drop of coolant in module MPa 0.31 0.21 0.31 0.29
Pressure drop in FW MPa 0.28 0.19 0.28 0.26
Pressure drop in sub-module MPa 0.033 0.02 0.031 0.03
2. Coolant velocity in FW outlet is fixed at
69m/s, to test the hydromechanics performance of
FW channel.
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Safety Analysis of CH HC-SB TBM

• Direction
• The relevant safety analysis is need to meet
  the requirements in GSSR and French Nuclear
  Safety Authority (NSA)
• For each component all the possible failure
  modes, in the various operating phases, will be
  evaluated.
• Progress
• Some results of safety analysis are presented in
  the CH HC-SB TBM DDD report last year.
• A safety working group (SWG) in China for
  licensing, QA and safety report of CH TBM, which
  consists of State Nuclear Safety Bureau, State
  Environment Protection Bureau and design
  institutions, will be organized soon.
• A systematic approach ( FMEA) will be
  established after determining all components and
  sub-systems

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Safety Analysis (cont)
Activation afterheat
Reliability analysis
E-M calculation model
E-M analyses
LOCA analyses
LOFA analyses
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VI. Test and RD plans
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Relevant RD plans
System Integration, Out-pile RD Module
fabrication technology Thermo-mechanical
integrity of module Thermo-mechanical
performance Thermal hydraulic research
In-pile RD Breeder/multiplier development
Irradiation technology development Irradiation
tests of blanket partial mockup
Tritium Recovery System Development Process and
system development for hydrogen pump, Coolant
purification system
Neutronics / Tritium Production Tests with 14MeV
neutrons Neutronics performance of
blanket mockup and improvement of analysis
accuracy
Material Development Irradiation data of RAFM
(CLAM), etc. Environmental effect, etc.
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Irradiation Test on High Flux Reactors

• China has built a High Flux Engineering
  Test Reactor (HFETR) in the China Institute of
  Nuclear Power (CINP) . HFETR is a largest one in
  Asia.
• Neutron Flux
• Thermal neutrons 6.21014 n/cm2sec
  (Elt0.625eV)
• Fast neutrons 1.7 1015 n/cm2sec
  (Egt0.625eV)
• 235U of 90
  enriched in U fuel.
• Total power
• 125 MW (th)
• In addition, there are two sets experiment
  reactors with power of 20MW and 40MW are
  constructing in CIAE and CAEP of China.
• These facilities and their ability are useful
  for the irradiation experiment of the TBM
  structure materials, tritium breeders, neutron
  multiplier etc.

High Flux Engineering Test Reactor (HFETR)
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High Temperature He Experiment Loop

• A High Temperature He Experiment Loop
  (HTHEL) with 700 OC and 8-10 MPa, which is useful
  for HC-SB TBM design and RD activities, is
  proposed to be built in SWIP.

HTHEL sketch map
He Test Loop for HTGR
China has built a high temperature gas-cooled
reactor (HTGR). The technologies and experiences
gained in HTGR project will be useful.
Temp. 900 OC, Total Power 10MW Pressure
3 MPa
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Solid Breeder Technology

• China has studied tritium-processing
  technology supported by national fusion program
  for many years. Knowledge accumulated in this
  field is useful for the TBM tritium technology.
• Two kinds of ceramic breeder(
  Li4SiO4 , Li2TiO3 ), are developing in China.

Fabrication sample of the Li4SiO4 pebbles
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General Design and RD Schedule for HC-SB TBM
Items 06 07 08 09 10 11 12 13 14 15 Day 1
Design Phase
Detail design
Engineering design
Materials Development
Ceramic Breeder, Li4SiO4 , Li2TiO3
Structural material , (RAFS steel)
Neutron multiplier, Be
Performance Testing
In-pile testing
Out--pile testing
Tritium Technology
Tritium Extraction Technology
Tritium permeation Barriers
Coolant purification simulation loop
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Time Schedule for CH HC-SB TBM Fabrication and
Test
Years 06 07 08 09 10 11 12 13 14 15
TBM Sub-components qualification.
Small mock-ups fabrication
Test/qualification
TBM Functional tests
Small and medium size mock-ups fabrication
Small and medium sizes mock-ups tests
Full size mock-ups fabrication
Full size mock-ups tests
EM-TBM for installation
CH EM-TBM fabrication
CH EM- TBM acceptance tests
ITER Operation Day one
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Proposed test facilities prior to TBMs
installation in ITER
Facilities name Main objectives Parameters Location
A high temperature He Experiment Loop based on China HTGR technologies. TBM mock-ups test 500-700 OC and 8-10 MPa (adjustable) SWIP/ (planning)
A facility for high heat flux properties test Evaluation of plasma facing materials and components Max. power density 20 MW/m2, Active cooling, control of the temperature of coolant from RT-150 SWIP/ (planning)
High Flux Engineering Test Reactor (HFETR) Materials Test Thermal neutrons 6.21014 n/cm2sec (Elt0.625eV) Fast neutrons 1.7 1015 n/cm2sec (Egt0.625eV) CINP/ (existing)
Facilities of tritium extraction, purification, permeation , and test Tritium extraction and recovery experiment from the purge gas and coolant. TBD CAEP, CIAE SWIP (planning)
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Work Breakdown Structure of HC-SB TBM
1. CH TBM Projects
1.1 Test Blanket Module
1.2 Ancillary System
1.3 Project Strategy
1.1.1 Design
1.2.1 Design, RD
1.3.1 QA Management
HCS
TES
1.1.2 Performance Analysis
1.3.2 Safety Licensing
CPS
MS
1.1.3 Technology Relevant RD
1.2.2 Testing integration Performance
1.3.3 Test Plane Management
1.1.4 Prototype Fabrication Testing
1.2.3 Fabrication Assembly
1.3.4 Testing Relevant RD
1.2.4 TBM integration installation
1.1.5 TBM Fabrication Assembly
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Expected Collaboration on TBM RD

• Tritium technologies
• - Tritium extraction
• - Tritium control and ISS
• - Tritium loop qualification
• - Tritium permeation Barriers
• Ceramic breeder technologies
• - Fabrication
• - Performance test
• - Irradiation test.
• Thermo-mechanics and helium flow test
• Test of on the pebble bed thermo-mechanics
  and helium flow stability and distribution by
  means of a high temperature, high pressure He
  test loop.

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Domestic Cooperation Units on RD for HCSB TBM
TUNET Tinghua Uni, Institute of Nucl. Energy
Tech. (HCS)
Ningxia Orient Non-ferrous Metal Group CO.,LTD
Be pebbles
SWIP Southwestern Institute of Physics (TBMs)
CAEP China Academy of Engineering Physics (CPS,
TES)
SICCAS Shanghai Institute of Ceramics, Chinese
Academy of Sciences (Ceramic Breeder)
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V. Summary

• New progress and status of CH HC-SB TBM are
  introduced briefly. By ITER TBM testing,
  demonstrative data of blanket functions will be
  obtained in fusion environment.
• A preliminary design and analysis for CH HC-SB
  TBM has been preformed The detailed design and
  analysis of EM-TBM are ongoing.
• Preliminary RD program, timescale and
  milestones, up to the installation in ITER
  (2015), as well as the collaboration expected
  with other Parties are presented.
• Relevant RD on the key techniques will be
  preformed with the cooperation of domestic and
  international institutions and companies.

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Thank you for your attention!