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Progress and Preliminary R&D Plans of China Solid Breeder TBM
Progress and Preliminary R&D Plans of China Solid Breeder TBM
K.M. Feng
Presented at 13th Ceramic Breeder Blanket Interaction Workshop – Santa Barbara, CA, USA
Nov. 30-Dec. 2, 2005
2
ContentsI. IntroductionII. Design Progress of CH HC-SB TBMIII. Preliminary R&D and Test PlansIV. Possible Collaboration with Other PartiesV. Summary
3
A description design and it’s performance analysis of CH HC-SB TBM have been carried out recently.
A design description document (DDD) of the HC-SB TBM have been completed recently. The relevant R&D, test plans based on the TBM design were proposed.
China hopes to widely collaborate with other ITER parties under TBWG framework, and expects to deliver a HC-SB TBM to ITER on day one. Possible collaboration field on TBM R&D with partiers have been given.
I. Introduction
4
II. Design and AnalysesII. Design and Analyses of of CH CH HCHC--SB TBMSB TBM
5
Present design is based on the ¼ port size on Port C;However, It is easily extended to a half-port-space module.
630mm(d) X 660mm(w) X 890mm(h)
Assumed Port Position for CH HC-SB TBM Module
HCS
TWCS
CH
6
Modular Design on StructureBe armor: 2 mm
Max Temp. 543OCFirst wall:thickness: 30 mm
Material: EuroferMax T: 530OCCooling tube: 18x14.5mm
Unit cells: 3X3 sub-modulesHe pressure: 8 MPa
664mm
Integration view of structure design
Sub-modules
0.190 m in toroidal0.420 m in radial0.260 m in poloidal
664mm
890mm
630mm
7
Main Characteristics
1. Modular structure design improve and strengthen the safety performance, reliability, maneuverability of test in ITER, and disassembly feasibility, more easy to replace the sub-module;2. The BOT with ceramic pebble bed concept, Be as neutron multiplier are used in the design; 3. A U-shaped double-shell FW structure is used;4. Each cell as a sub-module has relative independently cooling circuit (8 MPa He) and purge gas circuit (0.1 Mpa ). The cooling model in series connection from FW to sub-modules are used; 5. Each sub-module is a closed box by the top-lower plates with two side-plates.
8
Schematic view of CH HC-SB TBM
Outside of structure Cross-section of module Coolant manifold
Sub-module structure
Cross-section of sub-module
Configuration of Sub-modules
9
Exploded 3-D view of HC-SB TBM
Structure and components design in detail is on going.
10
section plane
Cooling tube of FW
Heat exchangerCoolant manifoldU-shaped double-shell FW structure
11
Interface Description
Test port general arrangement TBM module assembly
Equatorial test port area with transporter Transporter side wall pipe arrangement Equatorial port and pipe area
HCS sub-system in TCWS
12
Design parameters for the HC-SB TBM
13
HC-SB TBM Auxiliary Sub-system
TBM HCS CPS
VV Port Cell TWCS vault
Tritium Building
BC
TES
TMS
NMS
14
Schematic views of Coolant flow
Coolant flow in the sub-moduleToroidal cross-section Coolant flow in FW
Back-plate
Coolant Flow DirectionBreeding zone Arrangement Back-plate
15
HC-SB TBM Auxiliary Sub-system
21Flow scheme of the HCS system
HC-SB TBM
3 . 5 x2.5m2
Dust filter
Main HX
recuperator
Electric heater
Circulator
Valve
Draft layout of the helium cooling subsystem in the TCWS
TWCSHCSTBM
Helium Cooling System (HCS)
29
Neutron Measurement System (NMS)
Schematic diagram of neutron fluxes and spectra measurement system
micro-fission chamber
micro-fission chamber assembly 23Space Arrangement in TCWS for HCS subsystem
Space requirement:
A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed
Space requirement:
A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed
HCS TMS TES
CPS NMS TCWS27
Coolant Purification System (CPS)
1
3a
4
6 a 6b
7a 7 b
8
9
He , 30 0 ℃
3 00 ℃
H e, 1 0M P a
5
E S
E S
3b
1 0
H e
2a2 b
Layout of the CPS
Flow chart of the CPS
2200
1500
1200
1-gas flow controller; 2a/2b-impurities getter bed; 3a/3b-tritium getter bed; 4-heater; 5-cooler; 6a/6b-buffer bank; 7a/7b-ionization chamber;
8-gas chromatograph9—circulator; 10—ZrCo bed
Space requirement:A space of 1500mm×1200mm×2200mm (L×W×H) is neededfor its assembly, maintenance and operation of the CPS.
26
Tritium Extraction Subsystem (TES)
4b
9 b
34 a
E S
6
7
8 a 8 b
9 a 1 0
1 1 a
1 2
E S
1 3 a
1 4 b
1 4 a
9 c
1 5H e
1 1 b
1 6
H2
T r i t i u m E x t r a c t i o n S y s t e m fo r T B M
1 3 b
1 3 c
4 c
1
2 a
2 b
1 T B M2 a /2 b F i l t e r3 C o o le r4 a /4 b / 4 c I o n i za t i o n C h a m b e r5 C o ld T ra p6 W at e r C o l l e c to r7 R ec u p e r a to r8 a /8 b M o le c u l a r S ie v e s9 a /9 b / 9 c B u ff e r1 0 H o t M g B e d1 1 a /1 1 b C o m p r e ss o r1 2 P d /A g P e r m e a te r1 3 a /1 3 b /1 3 c G e t t e r B e d1 4 a /1 4 b I SS1 5 H e a te r1 6 M a k e - u p U n i t
Ch e c k v av l e
Op e n v a vl e
Cl o s ed va v l e
Pr e s su r e r e du c i n g v a v le
E S Ev a c ua t io n sy s t e m
± ±
± 5
V 1V 2
Flow chart of the TES sub-system Lay-out of the TES sub-system
Space Requirement:The TES system must be installed in a glove box.
The size of the Glove Box is: 5.5m×1.2m×5.5m (L×W×H).30
Tritium Measurement System (NMS)
The schematic of the gas flow calorimeter
Flow chart of the TMS
Layout of the TMS
16
a. Neutronics calculationsb. Activation analysisc. Thermo-hydraulic Analysis d. Thermo-Mechanical Analysise. Preliminary E-M analysis;f. Preliminary LOCA, LOFA analysis, etc.,
Above performance analysis have been completed. The results in detail have been given in the CH HC-SB TBM DDD document.
Performance Analysis
17
Performance Analysis (Con’t)
17
Temperature distribution ofthe HC-SB test module
First wall
Peak Temp. : 543 OC
Sub-module
Temp. Range: 624-737 OC in the breeder zone;Peak Temp.: 522°C in sub-module cooling plate 18
Stress distribution of the HC-SB test module
First wall Sub-module
Max. Stress are 244 MPa in FW and 219 MPa in sub-module cooling plate. This analysis result of the cooling plate in the test module satisfies to the requirements of structure strength regulations.
31
E-M and Accident Analyses
model induced eddy currents eddy currents vs. time
In-vessel LOCA shear stresses maximum stresses
15
Neutronics Calculation
TBR = 1.15(1-D, Li-6 enriched of 80%) Power: 0.76MWTritium production: 0.033g/dPeak power: 8.9 MW/m3
Neutron flux distribution
Power density
0.0
2.0
4.0
6.0
8.0
10.0
12.0
220.0 230.0 240.0 250.0 260.0 270.0
Radial dis tance from center of plas ma /cm
Ene
rgy
dens
ity /
MW
/cm
3
ONEDANT
TWODANT
MCNP
Tritium production
Neutronics Thermo-hydraulic Thermo-mechanical
Safety and reliability E-M and accident analysisFlow scheme
26
Safety and Reliability Analysis
Afterheat Activity
Deformation Equivalent Stress 27
Coolant Flow Scheme
18
III. Test and R&D plansIII. Test and R&D plans
19
Relevant R&D plans
Continuously improve HC-SB TBM designInterface of TBM, frame and auxiliary system design;Improve and develop relevant software and database;
Development of tritium measurement technology;
Development of neutron diagnostic technology;
20
Relevant R&D plans (Con’t)
Manufacturing of key componentsSome necessary R&Ds are being performed for the ITER
shielding blanket task in China. Relevant fabrication technologyobtained will be useful for manufacturing of key components of TBM:
(1) HIP technology for joining different materials, such as Be/Cu;(2) NDT inspection method;(3) High heat flux (HFF) test facility and method, etc.
21
The Structural Materials Development Strategy
Development of RAFMs for TBM in China is being performed;
Development of the ODS (oxide dispersion strengthened) steels and vanadium alloy steel are on going in China;
Long-term is to develop SiCf/SiC composites material for advanced fusion blanket concepts.
22
Ceramic Breeder and Neutron MultiplierChina has studied tritium-processing technology supported by
national fusion program for many years. Knowledge accumulated inthis field is useful for the TBM tritium technology.
Two kinds of ceramic breeder( Li4SiO4 , Li2TiO3 ), are developing in China.
Fabrication sample of the Li4SiO4 and Li2TiO3 pebblesFabrication of the ceramic powder
23
Equipments and Technique for Ceramic Breederin CAEP
Melting-spraying unit for the production of Li4SiO4 pebbles
Separation System Control System
γ-LiAlO2 pebbles
Li2ZrO3 Pebbles
24
Time schedule for ceramic breeder technologies
R&D Contents 2006 2007 2008 2009 2010 2011 2012 2013 2014
Designing of radiation capsule for material test, designing of tritium circuit
Tritium absorption and releasing behavior on tritium breeder
Property test ( mechanical,physical chemical and thermal property)
Structure and contents designing of tritium; breeder by computation simulation
Development of microspheres fabrication technique
2015
Development of radiation capsule for material test, development of tritium circuitProperty test ( radiation stability, tritium release behavior, tritium fabrication property)
Tritium breeder fabrication as designed by computation simulation
25
Development of Neutron Multiplier
Main Chemical Composition of CH 2# and US S-65C**
**Data from the Sixth Smelt Factory of Hunan Province.
China has also large yielding capacity of Be and relevant experiences of neutron multiplier.China has built Be fabrication and manufactory in Ningxia Orient Non-ferrous Metal Group Co. A new project, to develop high quality Be in China, is being implemented for ITER.
Type No. Elements (wt.%)Be BeO Fe C Al Mg
Grade 2# (CH) 99 0.80 0.05 - 0.075 0.015
S-65C VHP (US) 99 1.0 0.08 0.1 0.060 0.060
26
Development of Tritium Technologies
Development of tritium extraction technologyDevelopment of tritium extraction technology- Instrumentation development;- Hydrogen isotope separation;- Tritium extraction;- He coolant purification simulation loop;- Tritium control technology;- Tritium release behaviour and required purge gas conditions.
Theoretical simulation and assessmentTheoretical simulation and assessment-- Tritium cycle modelling (tritium permeation, tritium inventory).
27
Tritium Technologies (con’t)
Develop tritium permeation barrieramorphous TiN(TiC)films by IBAD;
Al2O3 film by ions coating-oxidation, CVD, explosive spray, etc.
- TPRF >1000 is obtained in specimen experiments.
- To be applied in practice in tritium permeation barrier.
Future R&D in the near future- Key technologies for components and subsystem - Tritium system loop test
28
Tritium Processing Equipments in CAEP
Electrolytic Cell Hydrogen Purification Unit
Promising H,T and impurities on line analytical tools
29
Tritium Permeation Barrier Study in CIAE
Process apparatus for the Fe-Al coating
Fe-Al layer
316L base
Microstructure of the Fe-Al coating
316L base
Fe-Al layer
0
20
40
60
80
100
0 20 40 60 80 100
与渗层表面距离(μm)
atom.%
Fe
Cr
Ni
Al
Mo
The composition profile in the coating
Fe-Al intermetallic compounds in the coating layer
30
Time schedule for tritium technologies
2006 2007 2008 2009 2010 2011 2012 2013 2014
Component structure optimization
Demonstration system
CECE tritiated water disposal
On line analytic tools :MGC,QMS,…
ISS: TCAP, PMS
2015
Tritium emergency-responsesystem
Tritium permeation barrier
Integration and test of realsystem
31
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 : 6.2×1014 n/cm2•sec; (E<0.625eV)Fast neutrons : 1.7 ×1015 n/cm2•sec; (E>0.625eV)
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)
32
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 R&D activities, is proposed to be built in China.
China has built a high temperature gas-cooled reactor (HTGR). The technologies and experiences gained in HTGR project are useful.
Temp.: 900 OC, Total Power: 10MW Pressure: 3 MPa
He Test Loop for HTGRHTHEL sketch map
33
Design and R&D Schedule for HC-SB TBMItems 06 07 08 09 10 11 12 13 14 15 Day 1
Design PhaseDetail design
Engineering design
Materials DevelopmentCeramic Breeder, Li4SiO4 , Li2TiO3
Structural material , (RAFS steel)
Neutron multiplier, Be
In-pile testing
Performance Testing
Out--pile testing
Tritium TechnologyTritium Extraction Technology
Tritium permeation Barriers
Coolant purification simulation loop
34
Small-sized HC-SB TBM mock-up tests (scale 1:4 or larger)
Ceramic pebble bed thermo-mechanical test
First wall heat removal test and thermal cycle test
Prototype TBM mock-up test
Heat removal test and thermal cycle test
TBM check-out with the auxiliary systems prior to ITER installation
Out-of-pile Test
35
Tritium release behavior and required sweep gas conditions;
Thermo-mechanical behavior of ceramic breeder and Be pebbles under neutron irradiation conditions;
Structure materials irradiation test;
Mechanical properties test of irradiated ferritic steel samples;
In-of-pile Test
36
Years 06 07 08 09 10 11 12 13 14 15TBM 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
Typical cost estimation : about 0.1-0.2 Billion Chinese Yuan for one CH HC-SB TBM.
ITER OperationDay one
Time Schedule for CH HC-SB TBM Fabrication and Test
37
Domestic Cooperation Units on R&D for HCSB TBM
SWIP Southwestern Institute of Physics
(TBMs)
SICCAS Shanghai Institute of Ceramics, Chinese Academy of Sciences
(Ceramic Breeder)
TUNETTinghua Uni, Instituteof Nucl. Energy Tech.(HCS)
TUNETTinghua Uni, Instituteof Nucl. Energy Tech.(HCS)
CAEPChina Academy of Engineering Physics(CPS, TES, Breeder )
CAEPChina Academy of Engineering Physics(CPS, TES, Breeder )
Ningxia Orient Non-ferrous Metal Group CO.,LTD
Be pebbles
38
V. SummaryV. Summary
New progress and status of CH HC-SB TBM since last TBWG meeting are introduced briefly.
Under the cooperation with domestic institutes, a preliminary design and analysis for CH HC-SB TBM module has been carried out. A design description document (DDD) have been completed recently.
Preliminary R&D program, timescale and milestones, up to the installation in ITER (2015), as well as the collaboration expected with other Parties are presented.
Relevant R&D on the key techniques will be preformed with the cooperation of domestic and international institutions and companies.
39
Thank you for your attention!