Current Status of Solid Breeder TBM in China
Presented by: Kaiming Feng
(On behalf of Chinese HCCB TBM Team)
Co-Institutes:
1). China Academy of Engineering Physics (CAEP), Mianyang, P.R. China
2). Chinese Institute of Atomic Energy (CIAE) , Beijing, 100084, P.R. China.
3). Chinese Institute of Nuclear Power（CINP), Chengdu 610043, P.R. China
4). Shanghai Ceramic Institute, Chinese Academy of Science (SCICAS), P.R. China
Presented at CBBI-16 meeting
Sep. 8 -10, 2011, Red Lion on the River , Portland, OR, USA
OUTLINE
1. Introduction
2. Progress on Updated Design
3. Progress on Relevant R&D
4. Test Plan and Cooperation
5. Summary
1. Introduction
 ITER is an unique opportunity to test tritium breeding blanket mock-ups in
an integrated tokamak operating conditions;
 Helium-cooled ceramic breeder (HCCB) test blanket module will be the
primary option of the Chinese ITER TBM program;
 China has the position of Port Master (PM) in port number 2 and is leading
the HCCB concept as the TBM Leader (TL). CN HCCB TBM will be tested
at different phases of ITER operation;
 In order to reduce the effects of magnetic field ripple, the TBM design was
updated with reduced RAFM mass;
 Related R&D on key components, materials, fabrication and mock-up test
have being implemented in China.
Roadmap to DEMO
 It was assumed that DEMO is a next step after ITER.
 DEMO will demonstrate the integration technology, materials, economics, safety, and
environment for the fusion energy applications.
 TBM testing on ITER is an important approach toward to DEMO.
CTF? FNST?
ITER -TBM
Power Plant
EAST
DEMO
ITER
IFMIF
HL-2A
2010
2020
Fusion Breeder?
2035
2050
HCSB-DEMO Blanket Concept
 As one options of breeding blanket with the Helium-cooled solid breeders/RAFM
steel (HCSB-DEMO) will be chosen as China’s DEMO blanket concepts.
 HCCB TBM will demonstrate the functions required for Chinese HCSB-DEMO
blanket under at ITER operation condition.
3-D View of HCSB DEMO blanket
.K.M.Feng, et.al., J. Fusion Eng.& Desgn, 84(2009)2109-2113.
5
HC-SB DEMO Blanket
TBM Concepts and Port-Sharing
Six TBM Systems to be installed in ITER in different operation phases
Port No. and PM
TBM Concept
TBM Concept
A (PM : EU)
HCLL (TL : EU)
HCPB (TL : EU)
B (PM : JA)
WCCB (TL : JA)
PMG: US/KO, LLCB? TL?
C (PM : CN)
HCCB (TL : CN)
LLCB (TL : IN)
PM : Port Master, TL : TBM Leader
HCLL : Helium-cooled Lithium Lead
HCPB : He-cooled Pebble Beds (Ceramic/Beryllium)
WCCB : Water-cooled Ceramic Breeder (+Beryllium) HCCB : He-cooled Ceramic Breeder (+Beryllium)
LLCB : Lithium-Lead Ceramic Breeder (LiPb & He, Dual-Coolant type)
CN HCCB TBM
CN HCCB TBM will demonstrate the functions required
for Chinese DEMO blanket in ITER condition
ITER cross-section
Relationship of ITER,TBM and DEMO
HCSB-DEMO
2. Progress on CN HCCB TBM Design
 A series of the Chinese HCCB TBM design have been carried-out since 2004 within the
space limitation and technical requirements specified by ITER.
7
Outline of HCCB TBM Design
Originally design of CN HCCB TBM have been completed
before 2009.
Basic design characteristics:
- TBM structure: Sub-module arrangement
- Structure material: RAFM (CLF-1);
- Tritium breeder: Li4SiO4 pebble bed, 80%Li-6 ;
- Neutron multiplier: Be pebbles bed;
- Coolant and purge gas: Helium gas
- Coolant pressure: 8MPa
- Coolant temperature: 300 OC(inlet) -500 OC (outlet)
- Tritium production ratio (TPR): 0.0505g/d
Integration View of CN HCSB TBM
Assembly scheme of Sub-Modules
Cross-section of SB
Updated Design of HCCB TBM for Reduction RAFM Mass
 Objectives of updated design:
- to simplify Sub-module structure;
- to reduce RAFM mass;
- to improve TPR performance;
 Results shown:
- The RAFM mass is reduced from
2.3t to 1.6t).
- TPR is increased by factor from
0.051g/day to 0.0798g/day.
 Main modification
-
HCCB TBM Module
TBM Sub-module arrangement
Cross-section of SM
Reduce radial dimension of the FW and sub-modules.
Bypass is introduced to TBM design to control the difference of
flow-rates .
Arrangement of pebble beds in the sub-module is changed from
the former transverse direction to the current vertical direction.
 An optimized all RAFM design with reduced mass of 1.3t is on going.
 A updated DDD report will be completed soon.
9
Exploded view of sub-module
Performance Analyses for Updated TBM Design
Tmax= 517 OC
a) RAFM material
Tmax= 548 OC
b) Be pebble bed
Tmax= 621 OC
c) Li4SiO4 pebble bed
d)Sub-module
Temperature Distribution of Sub-module
 Main calculation results
Previous
design
Updated
design
RAFM mass, ton
2.31
1.63
Tritium Production
Rate (TPR), (g/d)
0.051
0.079
Peak power density
(MW/m3)
6.26
6.82
Total power deposit
(MW)
0.587
0.642
Parameters
Temperature and stress distribution of FW
 Main parameters meet design requirement.
 TPR is obviously increased.
10
Performance Analyses for Updated TBM Design
Thermal analysis
Primary stress
thermal analysis model
Secondary stress
Thermal analysis results of sub-module
Stress analysis
RAFMs
(CLF-1)
Li4SiO4
pebble bed
Be pebble bed
Thermal
conductivity
[W/(m·K)]
29.8
(400 ℃ )
1.0-1.2
(500-900℃ )
5.4, 8.8, 10.6
(500, 600, 700
℃)
Max. allowable
temperature [℃]
550
920
700
CN HCCB TBM Auxiliary Sub-system Design
13
Design Parameters for the HCCB TBM
Basic configuration
BOT (Breeder Out of Tube)
Modules: 2×6 Sub-modules
First wall area
Neutron wall loading
Surface heat flux
0.484 m(W)×1.660 m(H)
0.803 m2.
0.78 MW/m2
0.3 MW/m2 (normal condition)
0.5 MW/m2 (extreme condition)
Total heat deposition
NT-TBM PI-TBM
0.642 MW
Tritium production rate
ITER operation condition
0.079g/FPD
TBM module dimension
(P)× (T) × (R)
1660mm×484mm×675mm
Ceramic breeder (Li4SiO4)
Single size
Thickness
Max. Temperature
D = mm, pebble bed
90 mm (four zones)
699℃
Neutron multiplier
(Beryllium)
Two size
Thickness
Max. Temperature
Diameter: 0.5~1 mm, Pebble bed
200 mm (five zones)
537℃
Structure Material
Ferritic steel
Max. Temperature
CLF-1
538 ℃
Coolant helium (He)
Pressure
Pressure drop
Temperature range (inlet/outlet)
Mass flow
Diameter (OD/ID)
8 MPa
0.08 MPa
300/500 ℃
1.36kg/s
101.6/85.5 mm
Pressure
Pressure drop
Mass Flow
Diameter (OD/ID)
0.12 MPa
0.02 MPa
0.6 g/s
35/30 mm
Pipes size
He purge flow (He)
CN TBS Integration with ITER (Con’t)
2 half-ports
C5
CN-HCCB
C6
IN-LLCB
15
View of Pipe Forest and TBM-Sets in Port #2
CN TBS Integration with ITER
Tokamak Coolant Water
System vault
Port Cell area
India part
Port Cell
(AEU)
Interspace
(Pipe forest)
Port 2#
(Port Plug)
L2 of Tritium building
for TES
China part
Interface 1 Interface 2a
Interface 2b
Interface 3
 Space reserved for CN TBS has been identified.
 Arrangements of CN TBS have been considered.
 Investigation of components which selected for CN TBS has
been done.
 Strategy for Pipe Forest maintenance has been coordinated
with IO people.
16
Space Arrangement Identification of CN TBS
Space arrangement
3. Progress on R&D: Structural Materials-CLF-1
Consumable electrode furnace
Remelting facility
 Two RAFM alloys are being developed in China; CLF and CLAM
A 500kg and 1-ton ingots of CLF-1 steel were recently produced
by vacuum induction melting and electro-slag remelting method.
 The optimization of the melting technique for the larger ingots to is
underway.
1-ton Ingot of CLF-1
17
Tensile strength of CLF-1
DBTT of CLF-1
500kg Ingot of CLF-1
3. Progress on R&D: Ceramic Breeder Pebbles
5000

Two kinds of ceramic breeders (Li4SiO4, Li2TiO3) for TBM are being
developed at different institutions in China;
Lithium orthosilicate (Li4SiO4 ) pebbles will be the primary option in the
CN HCCB TBM.
Li2CO3
Li2SiO3
4000
Internsity (Counts)

Li4SiO4
3000
2000
1000
0



15
Ceramic breeder (Li4SiO4) pebbles
fabricated by melt spraying method have
good sphericity, and high density.
Ceramic breeder (Li4SiO4) pebbles
prepared by Freeze-sintering process
have good mechanical properties (the
average crush load is 50N) ;
Li2TiO3 Pebbles have good surface
feature by using sol-gel method.
Li4SiO4 phase content
25
30
35
40
45
50
55
60
65
70
2
XRD pattern of Li4SiO4 pebbles
Li4SiO4 Pebbles (D=1mm)
by metl spraying method @SWIP
Main properties (Li4SiO4) by melt spraying method
Relative density
20
Li4SiO4 Pebbles (D=1mm)
by freeze-sintering method @CAEP
94% TD
90%
Closed porosity
0.72%
Open porosity
5.2 %
Average crush load
7.0 N
Specific surface area
1.092 m2/g
Li4SiO4 Pebbles (D=1mm) by
extrusion–sintering method @CIAE
18
Li2TiO3 Pebbles (D=1mm)@CAEP
3. Progress on R&D: Fabrication of Be Pebbles
Main chemical composition of Chinese Be 1#
Chinese
VHP-Be
Be
BeO%
Al
C
Fe
Mg
Si
Other metallic
elements
1#
≥99%
0.750
0.006
0.060
0.050
0.003
0.009
<0.04
 Be metal of high performance was
developed in China .
 Be pebbles have been produced by
Rotating Electrode Process (REP)
method in China. Related performance
tests are on going.
 A new project to develop higher
quality Be pebbles in China is being
implemented for the ITER project.
Chemical Composition of Be pebble
Be (wt%)
98.3
BeO (wt%)
1.67
Al (ppm)
235
Si (ppm)
18
Mn (ppm)
58
Mg (ppm)
≤10
Co (ppm)
≤10
Be Pebbles (D=1mm)
Micrographs of Be Pebbles (D=1mm)
REP Facility at HBSM Co.
Sample of Be Pebbles(D=1mm)
3. Progress on R&D: Helium Coolant Test Loop

The construction of a small He Test Loop to validate circulator technology will be completed soon.
- The He test loop has two impellers. It uses aerostatic bearings to avoid oil lubricating.
Main parameters of circulator design
Parameters
Circulator
Maximum flow rate
/kg-1s
Inlet pressure
/MPa
Maximum pressure head /MPa
He inlet/outlet temperature
/℃
~0.35
8
0.4
~50/65
Flow diagram of small He loop
3-D view of circulator
Impeller of circulator
A prototyped Helium Test Loop to validate TBM components and design is also to be built in
SWIP. The circulator will use magnetic bearings. The flow rate will up to 1.3kg/s.

Flow diagram of He Loop
Layout of He Loop
Cross-section view
Fabrication of Key Components of He Test Loop
21
3. Progress on R&D: Fabrication Process of U-Shaped FW
 A small-sized mock-up (1:3) of U-shaped first wall is completed;
 Two kinds of fabrication method of U-shaped FW have been considered;
22
3. Progress on R&D: Fabrication of Small Sized Mock-up
 A full-sized mock-up with 2X2 sub-modules arrangement using the RAFM steel (CLF-1)
as structure material will be completed in this year.
23
4. TBS R&D and Delivery Plan
1. CN HCCB TBS qualification activities
–
–
–
–
–
–
–
Helium experimental loop (1:3) construction (2010.01-2011.06)
Conceptual design of CN HCCB TBM(2010.01-2012.12)
CN TBM testing and update design (2011.06-2013.12)
Preliminary design of CN HCCB TBM (2013.01-2013.12)
Prototype helium loop construction (2012.01-2014.06)
Large scale TBM mock-up tests (2014.06-2015.12)
Final design of CN HCCB TBM (2014.01-2015.12)
2. CN HCCB TBS delivery activities.
– Main TBS components fabrication (2016.01-2017.06)
 Final TBS design in ITER.
 Main TBS components fabrication.
 TBS function tests (domestic).
– CN TBS delivery (2016.12-2017.06)
– CN TBS acceptance tests in ITER site (2017.06-2017.12)
– EM TBM delivery (2018.01-2018.06)
– EM-TBM System acceptance tests(2018.06-2019.06)
High flux test reactor
3. EM-TBM will be installed in ITER port after the first plasma shutdown (2019)
24
Domestic and Intl. Cooperation
 A lot of domestic units are joined into CN HCCB TBM program, including universities, institutes and
industry company
CN HCCB TBM
Design Team
SWIP
CIAE
XJTU
NCIRD
NPIC
SICCAS
CAEP
ASIPP
NCEPU
IMPCAS
TUINET
SJTU
R&D Team
SWIP
CIAE
ASIPP
XJTU
NPIC
SICCAS
CAEP
SJTU
NCEPU
IMPCAS
TUINET
HBSMC
Safe & QA Team
SWIP
CIAE
ASIPP
NPIC
NCIRD
CAEP
NCEPU
TUINET
TUINET
SICCAS
CAEP: China Academy of Engineering Physics;
CIAE: China Institute of Atomic Energy;
SJTU: Shanghai Jiao Tong University;
ASIPP: Institute of Plasma Physics; Academy of Sciences ;
NCEPU: North China Electric Power University;
NECB: Nuclear Engineer Corporation , Beijing
NPIC: Nuclear Power Institute, China;
IMPCAS: Institute of Modern Physics, Chinese Academy of Sciences;
TUINET: Tsinghua University, Institute of Nuclear Energy Technology; XJTU: Xi’an Jiao Tong University;
25
SICCAS: Shanghai Institute of Ceramics, Chinese Academy of Sciences ; HBSMC: Haibao special metal materials Co.
Domestic and Intl. Cooperation
Intl. Cooperation and Partnership
 CN HCCB TBM will be operated and tested on ITER through international
cooperation under the frame of partnership with ITER parties.
 China is interested in other TBM concepts as a partner in HCPB-TBM,
WCCB-TBM and LiPb-based TBMs.
 China HCCB TBM is open to cooperation with other ITER parties. Some
informal discussions, for instance, CN-EU,CN-JA, CN-KO, has been started.
 CN-US bilateral cooperation meeting on TBM program will held on Nov.7-9,
2011.
5. Summary
 HCSB TBM with the Solid Breeder/Helium coolant/ RAFM material is the
primary option of the Chinese TBM program.
 Updated design, current progress on R&D, test and delivery plan up to the
installation in ITER (2019) are presented.
 Relevant R&D on key techniques for the HCSB TBM concept are supported
by the Chinese ITER- DA domestic agency (2009-2012) , including:
–
–
–
–
–

TBM optimization design and validation of key technologies;
Fabrication of Li4SiO4 pebbles and Be pebbles to large-scaled level;
Fabrication of structure material RAFM to ton level;
Construction of High Heat Flux Test Facility (Power:400kW);
Construction of small-scale and prototyped Helium Test Loop.
Testing HCSB TBM on ITER will be implemented with the cooperation of
domestic and international institutions and industries.
Thanks for your Attention !