current status of chinese solid tritium breeder tbm
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1
Current Status of
Chinese Solid Tritium Breeder TBM
Presented at Sixth PRC/US Magnetic Fusion Collaboration Workshop
July 10 -12, 2012, University of California, Sen Deigo, USA
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
5). Haibao Special Metal Materials Co.(HSMM) , Baoji, P.R. China
2
Outline
1. Background
2. Progress on TBM Design
3. Progress on TBM R&D
4. R&D Plan and Collaboration
5. Summary
3
1. Background
ITER is an unique opportunity to test tritium breeding blanket mock- ups in integrated Tokamak operating conditions.
Helium-cooled ceramic breeder (HCCB) test blanket module (TBM) will
be the primary option of the Chinese ITER TBM program. China has a formal position of Port Master (PM) in port number 2 and is
leading the HCCB concept as the TBM Leader (TL). Chinese solid TBM will be tested at different phases of ITER operation.
In order to reduce the effects of magnetic field ripple, the TBM design has been updated with reduced RAFM mass recently.
Related R&D on key components, materials, fabrications and mock-up test have being implemented in China.
China plan to sign HCCB TBM-A based on IO schedule (before June, 2013).
4
ITER TBM Concepts and Port-Sharing
Six TBM Systems to be installed in ITER three test ports
Port No. and PM TBM Concept TBM Concept
A (PM : EU) HCLL (TL : EU) HCPB (TL : EU)
B (PM : JA) WCCB (TL : JA) HCCB(TL:KO)
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 will demonstrate the functions required
for Chinese DEMO blanket in ITER condition
HCSB-DEMO ITER cross-section
CN HCCB TBM
Relationship of ITER,TBM and DEMO
6 6
A series of the Chinese HCCB TBM design have been carried-out since 2004 within the
space limitation and technical requirements specified by ITER.
Progress on CN HCCB TBM Design
7
Outline of HCCB TBM Design
- 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 HCCB TBM
Cross-section of SB
Assembly scheme of Sub-Modules
Basic design characteristics:
Original design of CN HCCB TBM has been completed before
2009.
8 8
Updated Design of HCCB TBM for Reduction of the RAFM Mass
HCCB TBM Module TBM Sub-module arrangement Cross-section of SM
- The RAFM mass is reduced from
2.3 to 1.6 tons ).
- TPR is increased from 0.051 to
0.0798g/day.
Objectives of updated design:
- to simplify Sub-module structure;
- to reduce RAFM mass;
- to improve TPR performance;
Exploded view of sub-module
Main modifications
An optimized RAFM design with reduced mass of 1.3t is on going.
An updated DDD report will be completed soon.
Results shown:
- 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.
9 9
TES
HCS CPS
TES
HCS
Cryostat
Vacuum
T-Building L2
T-Building L4,
Vault Annex
Gallery
Primary
Vacuum
Port Cell AEU
Bio-shield
Block
Shield
Block TBM
Cryostat
Bio-shield
Inter-space
VV
Control Room
ITER CCWS
ITER
Tritium
System
ITER
Tritium
System
Pipe
forest
CN HCCB TBS consists of TBM module and several ancillary sub-systems
HCCB TBM Auxiliary Sub-system
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Integration and Interface in AEU
Pipes
Pipes
IN components CN components
Valves and Pipes
The integration design and analysis in AEU including thermal-hydraulic analysis, mechanical
analysis, seismic analysis, according to RCC-MR code have been completed.
13 13
500kg Ingot of CLF-1
1-ton Ingot of CLF-1
3. Progress on R&D: Structural Materials-CLF-1
Consumable electrode furnace
Two RAFM alloys have being developed in China; CLF-1 in SWIP
and CLAM in ASIPP
1-ton ingot of CLF-1 steel were recently produced by vacuum
induction melting and electro-slag re-melting methods.
The optimization of the melting technique for the larger ingots to 3
tons is underway.
Tensile strength of CLF-1 DBTT of CLF-1
Remelting facility
14
3. Progress on R&D: Ceramic Breeder Pebbles
Relative density 94% TD
Li4SiO4 phase content 90%
Closed porosity 0.72%
Open porosity 5.2 %
Average crush load 7.0 N
Specific surface area 1.092 m2/g Li2TiO3 Pebbles (D=1mm)
by Sol-gel method@CAEP
Li4SiO4 Pebbles (D=1mm) by
Extrusion–sintering method @CIAE
Two kinds of ceramic breeders (Li4SiO4, Li2TiO3) for HCCB TBM are
being developed at different institutions in China;
Lithium orthosilicate (Li4SiO4 ) pebbles will be the primary option in the
CN HCCB TBM. The Li2TiO3 will be a candidate tritium breeder.
Li4SiO4 Pebbles (D=1mm)
by metl spraying method @SWIP
Li4SiO4 Pebbles (D=1mm)
by freeze-sintering method @CAEP
Melt spraying method for Li4SiO4 have
good sphericity, and high density.
Freeze-sintering process for Li4SiO4
have good mechanical properties ;
Sol-gel method for Li2TiO3 Pebbles have
good surface feature .
XRD pattern of Li4SiO4 pebbles
Main properties (Li4SiO4) by melt spraying method
15 20 25 30 35 40 45 50 55 60 65 70
0
1000
2000
3000
4000
5000
Inte
rns
ity
(C
ou
nts
)
2
Li4SiO
4
Li2SiO
3
Li2CO
3
15
3. Progress on R&D: Fabrication of Be Pebbles
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 has been 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 has being implemented for the ITER project.
Main chemical composition of Chinese Be 1#
Be Pebbles (D=1mm)
Micrographs of Be Pebbles (D=1mm) REP Facility at HBSM Co.
Be (wt%) 98.3
BeO (wt%) 1.67
Al (ppm) 235
Si (ppm) 18
Mn (ppm) 58
Mg (ppm) ≤10
Co (ppm) ≤10
Sample of Be Pebbles (D=1mm)
Chemical Composition of Be pebble
16
3. Progress on R&D: Related Tritium Technologies
• Related R&D of the tritium technologies of Chinese solider breeder TBM have
being developed at CAEP and CIAE.
The PRF of the tritium permeation barrier samples
Electrochemical Al (ECA) coating glove box Iron chambers for tritium analysis
20um coating on surface of RAFM)
0 5 10 15 20 25
0
10
20
30
40
50
60
70
80
90
Cr
Fe
AlCo
mp
ositio
n/a
t.%
Depth/um
17
3. Progress on R&D: Helium Coolant Test Loop
Flow diagram of He Loop Layout of He Loop
The construction of a small He Test Loop to validate circulator technology will be completed this year.
- The He test loop has two impellers. It uses aerostatic bearings to avoid oil lubricating.
Flow diagram of small He loop
Parameters Maximum flow rate
/kg-1s
Inlet pressure
/MPa
Maximum pressure head /MPa He inlet/outlet temperature
/℃
Circulator ~0.35 8 0.4 ~50/65
A prototyped Helium Test Loop to validate TBM components and design is also to be built in
SWIP. The flow rate will up to 1.3kg/s.
Fabrication of Impeller Impeller of circulator
Cross-section view
Main parameters of circulator design
18 18
3. Progress on R&D: Fabrication Process of U-Shaped FW
A small-sized mock-up of U-shaped first wall fabrication is completed;
Two kinds of fabrication method (EBW, HIP) of U-shaped FW have been considered;
Full sized mock-up of U-shaped first wall is under way.
Fabrication Process of U-Shaped FW
19 19
3. Progress on R&D: Fabrication of Medium 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 (1:3 in the height, 1:1 for others)
ITER Operation and TBM Test Schedule
2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 2027 2028 2029 2030
Construction First Plasma Hydrogen Helium Phase Complete Deuterium Phase Complete
ITER Commissioning and Operations
Start Torus Pump Down
Pump Down & Integrated Commissioning
First Plasma
Plasma Development and H&CD Commissioning
Nuclear License
Blankets Divertor
DT Hybrid Scenario
DT Non Inductive
He H-Mode Studies
Pre-Nuclear Shutdown & Divertor Change
DT Plasma Exploration & DT H-Mode Studies
Shutdown
Q=10 Q=10 Long Pulse
End of Magnet Commissioning
Phase 2 Machine Assembly
Commission, Cool & Vacuum Plasma Restart
Phase 3 Machine Assembly / Regulatory Shutdown
Full H&CD, TBM & Diagnostics Commissioning Full Heating Power @ Short Pulse N Licensing validation
100% T-fuelling capability
D Plasmas on W Divertor
D H-Mode Studies
Trace-T Studies
100% Tritium throughput capability
All TBMs installed
TBMs installation
EM-TBM
TN-TBM
NT/TM-TBM
INT-TBM
22
R&D Plan and Time Schedule
1. CN HCCB TBS qualification activities – Helium test loop construction (2011.01-2012.12)
– Conceptual design of CN HCCB TBM (2010.01-2012.12)
– Small-sized (1:3) TBM mock-up tests (2011.06-2012.12)
– Preliminary design of CN HCCB TBM (2013.01-2013.12)
– Prototype helium loop construction (2012.01-2014.06)
– Large scaled TBM mock-up tests (2014.06-2014.12)
– 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 (in domestic).
– CN TBS delivery (2017.01-2017.06)
– 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)
3. EM-TBM will be installed in ITER port after the first plasma (2020)
22
CN HCCB TBM
23
Domestic and Intl. Collaboration
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;
SICCAS: Shanghai Institute of Ceramics, Chinese Academy of Sciences ; HBSMC: Haibao special metal materials Co.
Design and analyses
( module, system,integration)
Material develop, tritium
technology, components,
mock-up,
Assembly ,safe & QA, test,
interface with ITER,
maintenance
China TBM Program
A lot of domestic institutions, universities and companies are joined into CN HCCB TBM program,
including industry companies
China is interested in other TBM concepts as a partner in HCPB, WCCB, LLCB 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, CN-IN have being processed.
CN-US bilateral meeting on TBM program collaboration has held in last year.
24
R&D Strategy for CN TBM Development
In/Out-of-pile
Component
Tests
Basic Material
Development
Sub-modules
In-pile Tests
RAFM(CLF-1), Tritium permeation barrier
Beryllium pebble, Ceramic Breeder
High temperature
/pressure He test
loop construction
Neutron
irradiations
TBM Design ,R&D, Mock-up
Integration, Test on ITER D
EM
O B
lan
ke
t D
es
ign
an
d D
eve
lop
me
nt
Pebble-Bed
Tests
TBM Interface
with ITER
DEMO TBS
integration
Thermal behaviour, Flow
Mechanical behaviour
He loop
High flux test reactor
Planed SWIP-US Cooperation on ITER-TBM
and Safety (2010-2012)
No. Topics To From Contents Status
C ITER-TBM
C-1.2 ITER He cooled TBM
Design
SWIP GA TBM structure, thermo-hydraulic, safety
analysis fields.
Yes
C-2 R&D for He cooled
solid breeder blanket
Design
SWIP UCLA Ceramic pebble bed purge flow tests and
simulation, safety analysis for CN HCCB
TBM
Yes
C-4.1 ITER He cooled TBM
Design
GA SWIP TBM structure, thermo-hydraulic, safety
analysis fields.
NO
C-5.1 R&D for He cooled
solid breeder blanket
Design
UCLA SWIP Ceramic pebble bed purge flow tests and
simulation, safety analysis for CN HCCB
TBM
NO
C-5.2 Therom-mechanics
tests for pebble bed
UCLA SWIP Pebble bed thermo-mechanics test, etc. NO
D Safety cooperation for fusion facilities
D-1.1
D-1.2
JWG on Safety SWIP
ASIPP
PPPL,GA,
INL
US Members visit China , 2009 and 2011 2009,Yes
D-1.3
D-1.4
JWG on Safety PPPL,
GA, INL
SWIP
ASIPP
CN Members visit US, 20210 and 2012 2010,Yes
25
Summary of SWIP- US Magnetic Fusion Collaboration
on ITER-TBM and Safety( 2010-2012)
C-1.2 ITER Helium cooled TBM
October 6-7, 2011, Dr. C. Wong visited SWIIP, exchanged on the design status on HCCB
and DCLL TBMs.
C-2 R&D for Helium cooled solid breeder blanket design
Prof. Alice Ying (UCLA) visited SWIP, exchanges were made on the solid breeder blanket
design at SWIP
C-4.1 ITER Helium cooled TBM Design (PRC to US, NOT EXECUTED)
November 14-16, 2011, Dr. C. Wong (GA) visited SWIP, exchanges were made on the
HCCB and DCLL TBMs. (PRC to US, NOT EXECUTED)
C-5.1 R&D for Helium cooled solid breeder blanket design
Nov.7-9, 2011, CN -US bilateral meeting on TBM program collaboration , the cooperation
feasibility on TBM design and related R&D were discussed.
C-5.2 thermo-mechanics tests for pebble bed (PRC to US, NOT EXECUTED)
D-2.1 PRC-US Joint Working Group (JWG) on Safety
November 4 -9, 2010, Profs. Qiang Li and K.M. Feng visited PPPL and GA, exchanged
were made on fusion facilities safety .
D2.2 US delegation to PRC , NOT EXECUTED yet, 2011.
National Spherical Torus Experiment
(NSTX)
CN HCCB TBM
US HCCB TBM PRC-US TBM workshop
Proposed Cooperation on TBM and Fusion Technology
Design, Analysis, and Safety of Ceramic Breeder TBS
Structure materials RAFM, fabricating, joining and welding technology
Tritium transport modeling in ceramic breeder TBM
Pebble and Tritium related technologies
– Tritium permeation barriers, relevant tritium technologies
– Neutron multiplier, Be pebble fabrication
– Ceramic tritium breeder Characterization
Experiments
– Irradiation test under the fission reactor condition (HFIR)
– Test of the pebble bed thermo-mechanics and helium flow stability and
distribution by means of a high temperature, high pressure He test loop.
TBM related tritium processing technology (particularly in low tritium concentration
process)
•
27
After China signed TBM-A with IO, following cooperation items should
be considered under the different collaborative format .
28
5. Summary
Solid breeder conceptual TBM is the primary option of the Chinese ITER TBM program.
Preliminary design for reducing RAFM mass has been completed. Farther
optimization design is underway.
R&D progress on development of structure material (CLF-1), fabrication of function materials (Ceramic tritium breeder, neutron multiplier Be pebble), and construction of He test loops, medium-sized mock-up of first wall and sub-module are presented.
The test plan and delivery time are scheduled.
Chinese TBM program will be implemented with the cooperation of domestic and international institutions and industries.
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