Progress and Status of ITER Solid Breeder Test Blanket Module in in China

Transcription

1 Progress and Status of ITER Solid Breeder Test Blanket Module in in China Presented By: Kaiming Feng (Southwestern Institute of Physics, Chengdu, China) Presented at 14th International Workshop on Ceramic Breeder Blanket Interaction, Sep. 6-8, 2006, Petten, The Netherlands 1

2 Outline I. Background II. Progress and Status III. R&D Plans IV. Summary 2

3 I. Background Development and test different ideas of ITER-TBM, it should be one of the aims of the ITER Project. China plans to develop own TBM concept for testing during ITER operation period based on China s DEMO definition and development strategy. The preliminary design and performance analysis of HC-SB TBM have been carried out. The final DDDs have been finished, moreover, related R&D plans are proposed. 3

4 Selection of DEMO Blanket in China Two options of breeding blanket with ceramic and lead lithium-lead breeders might be chosen as China s DEMO blanket concepts. HC-SB DEMO Blanket(SWIP) DFLL DEMO Blanket(ASIPP) 4

5 Selected HCSB-DEMO Parameters Chinese HC-SB Demo Parameters Fusion power/electric power, (MW) 2000 / ~ 600MWe Major radius, (m) 7.0m Minor radius,(m) m Neutron wall load,(mw/m 2 ) ~ 2.0 Surface heating,(mw/m 2 ) ~ Tritium breeding ratio,(tbr) >1.1 Availability, (%) Divertor peak load, (MW.a/m 2 ) 8.0 (water-cooled) Plasma operation mode Continuous 5

6 Basic Options on China TBM Solid Breeder Blanket might be a basic option and first candidate in China. The lithium-lead breeding blanket is also recommendable concept. We are also interested in other TBM concepts, such as, water-cooled solid breeder concept, etc. China is proposing two TBM concepts (HCSB, DFLL) to be tested in one port, with a unified design of auxiliary systems. 6

7 II. Design Progress of CH HC-SB ITER-TBM TBM 7

8 Originally Design of CH HC-SB TBM 2004 Version, ¼ Port,Integration design 8

9 Be Solid Breeder Back-plane He He 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) Outline view for CH originally HCSB-TBM design 9

10 Modified Design of HC-SB TBM (2005 Version, 3x3 Modularization Design) Configuration: Configuration: BOT BOT Be Be armor: armor: 2 2 mm mm Max Max Temp. Temp O O C C First First wall wall thickness: thickness: mm mm Material: Material: LAFM LAFM Max T: 506 O C Max T: 506 O C Coolingtube: Coolingtube: 18x14.5mm 18x14.5mm Unit Unit cells: cells: 3X3 3X3 sub-modules sub-modules He He pressure: pressure: 8 8 MPa MPa 10

11 Modification Design of HCSB-TBM 2006, ½ Port, 3x6 Modularization Design

12

13 Black-plate Design

14 Connection of Components,gap FW attachment Gap structure Cross-section of Sub-module 14

15 Assembly of HC-SB TBM in port frame 15

16 first wall grid sub-module backplate support plate Be pebble bed Li 4 SiO 4 pebble bed He supply pipe purge gas supply pipe purge gas return pipe He return pipe 3-D sketch map flexible support shear key 16

17 Schematic views of Coolant flow Coolant flow in FW Coolant Flow Direction Coolant flow in the sub-module 17

18 HCSB TBM integrated assembly (Common share the ancillary system) 18

19 HC-SB TBM Auxiliary System VV Port Cell TWCS vault HC-SB TBM BC HCS CPS TMS Tritium Building NMS TES 19

20 ¹ 2b He,10MPa 300 æ 2a 1 7a 6a 5 ES ES 8 6b 7b 4 He,300 æ 3a 10 3b He 1 H2 He 16 11b 4b V2 V1 4a 2b 3 2a 1 TB M 2a/2b Filter 3 C ooler 4a/4b/4c Ionization Chamber 5 C old Trap 6 Wat er Colle ctor 7 Recuperator 8a /8b Mole cular Sieves 9a/9b/9c Buffer 10 Hot Mg Be d 11a/11b Compressor 12 Pd/Ag Permeate r 13a/13b/13c Getter Bed 14a/14 b ISS 15 Heater 16 Ma ke-up Un it 6 15 ES 7 8a Check v avle Op en v a vl e Cl os ed va vl e Pressur e reducing vavle ES Evacuation system 4c ES 8b 13a 11 a 12 9b 13b 9c 14a 14 b 13c HC-SB TBM Auxiliary Sub-system Design Helium Cooling System (HCS) Tritium Measurement System (NMS) Tritium Extraction Subsystem (TES) TBM HCS TWCS Circ ulato r Dust filter À À 9a 10 HC-SB TBM Electr ic heater recup erator 3.5x 2.5m 2Va lve Main HX Flow chart of the TMS À 5 Tritium Extraction System for TBM Flow scheme of the HCS system Draft layout of the helium cooling subsystem in the TCWS 21 The schematic of the gas flow calorimeter Layout of the TMS HCS TMS TES 30 Flow chart 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 Á1.2m Á5.5m (L ÁW ÁH). Lay-out of the TES sub-system 26 Coolant Purification System (CPS) Neutron Measurement System (NMS) 2200 micro-fission chamber 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 Flow chart of the CPS Space requirement: A space of 1500mm Á1200mm Á2200mm (L ÁW ÁH) is needed for its assembly, maintenance and operation of the CPS Layout of the CPS 27 Schematic diagram of neutron fluxes and spectra measurement system Space Space requirement: A minimum minimum net net foot foot print print area area of of m 2 2 in in the the TCWS TCWS vault, vault, 0.5m 0.5m 3 3 in in transfer transfer cask, cask, will will be be needed needed Space Arrangement in TCWS for HCS subsystem micro-fission chamber assembly29 23 CPS NMS TCWS 20

21 Neutronics Measurement System (NMS) micro-fission chamber Schematic diagram of neutron diagnostic system 21 micro-fission chamber assembly

22 Tritium Measurement System (TMS) Flow chart of the TMS The schematic of the gas flow calorimeter 22

23 Items NT-TBM EM-TBM Configuration BOT (Breeder Out of Tube) Modules: 3 6 Sub-modules Modules: 3 6 Sub-modules First wall area Neutron wall loading Surface heat flux m(w) m(h) m MW/m MW/m 2 (normal condition) 0.5 MW/m 2 (extreme condition) Total heat deposition surface heat flux included 0.76 MW MW Globe TBR Lithium orthosilicate, Li 4 SiO (3-D), 80% Li-6 Tritium production rate ITER operation condition g/d (Vertical) MW/m 2 (normal condition) 0.3 MW/m 2 (extreme condition) Sub-module dimension (P) (T) (R) 253 mm 130mm 420 mm 253 mm 130mm 420 mm Ceramic (Li 4 SiO 4 ) Neutron multiplier (Beryllium) Be armor Structure Material Coolant helium (He) Pipes size He purge flow (He) breeder Design parameters for the HC-SB TBM One size Thickness Max. Temperature Two size Thickness Max. Temperature Thickness Max. Temperature Ferritic steel Max. Temperature Pressure Pressure drop Temperature range (inlet/outlet) Mass flow Diameter (OD/ID) Pressure Pressure drop Diameter: 1 mm, pebble bed 90 mm (four zones) 742 Diameter: 0.5~1 mm, Pebble bed 200 mm(five zones) 613 2mm 550 LAFM MPa 0.22 MPa 300/ kg/s 85/80 mm 0.12 MPa 0.02 MPa SiC pebble bed, 01 mm Al pebble bed, 0.5~1 mm 2mm 514 LAFM MPa MPa 300/ kg/s 85/80 mm 23

24 III. Performance Analysis for HCSB ITER-TBM TBM 24

25 3-D MCNP Model for Neutronics Calculation planform view TBM ITER side view planform view ITER side view 20 o planform view 25

26 Performance Analysis for HC-SB TBM Temperature distribution of FW Temperature distribution of sub-module Temperature on Flow Channel Stress distribution of FW Stress distribution of sub-module The stress distribution 26

27 Safety Analysis of HCSB-TBM Design Safety Analysis of CH HC-SB TBM (cont.)? activity and decay heat analysis Safety Analysis for CH HC-SB TBM (cont.)? LOCA and reliability analysis E-M Calculation Model At shutdown, the total decay heat is ~8.77 Á10-3 MW with a contribution of 8.71 Á10-3 MW and 6.36 Á10-5 MW from structure material and Li 4 SiO 4, respectively. Pressure transients from different models vs. time Deformation Equivalent Stress Total activity generated and contribution from each material A total activity of Ci is attained at shutdown with a contribution of 5.39 Á10 5 Ci from the structure, Ci from the Li 4 SiO 4. LOCA analysis shows depressurization of the TBM helium coolant occurs within 10 to 15 s. Contribution to the pressure build-up in the VV is small (17.8 kpa). Tritium and activation products released from the TBM into the VV are insignificant compared to the total amount mobilized from non-tbm components. The TBM FW temperature can be kept, after the disruption burst has decayed variant to the reference case, with postulated unlimited steam access to the pebble beds, the estimated hydrogen production is the order of g only and the chemical heat is negligible. 38 Temperature changes of materials after the end of blow-down 33 Total afterheat generated from each material 36 Activation & afterheat Reliability analysis E-M calculation model EM Analysis for the Centered Disruption Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOCA analysis for EM-TBM Plasma disruption: in-vessel TBM coolant leaks Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOFA analysis for EM-TBM Plasma no disruption: ex-vessel TBM coolant leaks The distributions of stresses in toroidal direction The distributions of the induced eddy currents The distributions of shear stresses in radial and toroidal direction The maximum stresses components The maximum induced eddy currents The EM torque of the total TBM module 32 Temper at ur e/ o C Fi r st Wal l Back Wal l Hottest Point e= Ti me/ s This figure shows temperature changes of materials after the end of blow-down. When heat radiation emissivity of material is 0.7, the peaking value of FW is about 623 O C at the transient time of about 1s. Temper at ur e/ o C Fi r st Wal l Back Wal l Hottest Point e= Ti me/ s This figure shows temperature changes of materials after the end of blow-down. When heat radiation emissivity of material is 0.3, the peaking value of FW is about 623 O C, too, at the transient time of about 1s. But curves have different change trends after 1000s. 44 Temper at ur e/ o C 1000 e= Fi r st Wal l Back Wal l 700 Hottest Point Ti me/ s Temperature/ o C Fi r st Wal l Back Wal l Hot t est Poi nt e= The two figures show temperature changes of materials after loss of flow accident. The smaller heat radiation emissivity of material is, the rapider temperatures of material increase. Under this accident condition, the auxiliary cool system is necessary to decrease the temperature of TBM shell. E-M analyses LOCA analyses LOFA analyses Ti me/ s 27 45

28 Safety analysis /RELAP5 Application Southwestern I nstituteof Physics, China Southwestern I nstituteof Physics, China Piping hydrodynamic model Piping between HCS components Model of main inlet manifold Model of First Wall(Poloidal-radial) Pipe Li 4Si O4 Li 4Si O4 FW He Be He He Be He He Be He He Be He He Be Li 4Si O4 Li 4Si O4 poloidal r adi al ITER Southwestern I nstituteof Physics, China 5. Results of in-box LOCA for EM HCSB TBM SWIP TBM GROUP ITER Sub Module under modeled Model of intermediate manifolds SWIP TBM GROUP SouthwesternInstituteof Physics,China 4. Results of Steady State EM HCSB TBM Pump velocity(rad/s) ITER 600 pump Time(s) Pump velocity of in-box LOCA Mass flow rate(kg/s) Time(s) TBM inlet TBM outlet valve 201 Mass flow rate of in-box LOCA SWIP TBM GROUP Temperature(? ) ITER Time(s) Circulator FW outlet Sub module inlet TBM inlet TBM outlet Temperature of Steady State Pressure(Pa) 8.07x x x x x x x x x x x Time(s) Circulator FW outlet Sub module inlet TBM inlet TBM outlet Pressure of Steady State SWIP TBM GROUP 28

29 Source Source data data Decay Decay γγ -source -source 3-D 3-D model model MCNP MCNP MC-FDKR MC-FDKR Nuclear Nuclear data data INPUT DATA INPUT DATA FDKR FDKR ACTIVATION ACTIVATION & & DECAY DECAY DATA DATA Decay Decay γγ -source -source FDKR-MC FDKR-MC MCNP- FDKR 3-D Activation Calculation Code

30 VI. R&D Plans on HCSB-TBM 30

31 Relevant R&D plans System System Integration, Integration, Out-pile Out-pile R&D R&D Module fabrication technology In-pile In-pile R&D R&D Module fabrication technology Thermo-mechanical Thermo-mechanical integrity integrity of of module module Breeder/multiplier Breeder/multiplier development development Thermo-mechanical Thermo-mechanical performance performance Irradiation Irradiation technology technology development development Thermal Thermal hydraulic hydraulic research research Irradiation Irradiation tests tests of of blanket blanket partial partial mockup mockup Tritium Tritium Recovery Recovery System System Development Development Process Process and and system system development development for for hydrogen hydrogen pump, pump, Coolant Coolant purification purification system system Material Material Development Development Irradiation Irradiation data data of of structure structure materials materials (CLAF), (CLAF), etc. etc. Environmental Environmental effect, effect, etc. etc. Neutronics Neutronics / / Tritium Tritium Production Production Tests Tests with with 14MeV 14MeV neutrons neutrons Neutronics Neutronics performance performance of of blanket blanket mockup mockup and and improvement improvement of of analysis analysis accuracy accuracy 31

32 Development Strategy for the structural materials Two sorts of structural materials will be focused on: - RAFM for ITER-TBM and DEMO-TBM (1) Data base to support the design, (2) Goal: support the fabrication in future - Low activation V-based alloys (1) For advanced fusion reactor blanket concept (2) Basic study on mechanism Budget (Total is about 4 M$) - A small part is from the Nuclear Energy Project. - Others will be supported by the MOST, as one of the projects in ITER program. Collaborations - SWIP and ASIPP will be the leading institutes in China - CIAE, IMR, NPIC and Universities will join. - International, join IFMIF. 32

33 R&D of China RAFM CLF-series (1) Chemical Composition, wt% C Mn S P Cr Ni Mo V Nb Cu W O N Ta CLF-1 (F82) < CLF-2 (Eurofer97) < (2) Mechanical property Type Tensile strength Yield strength Tensile ductility Impact ductility, σ b (MPa) σ 0.2 (MPa) δ (%) A k (J/cm 2 ) CLF-1 (~15%CW) >300 CLF-2 (~15%CW) >300

34 Development of Neutron Multiplier(Be) Main Chemical Composition of CH 2# and US S-65C ** Type No. Elements (wt.%) Be BeO Fe C Al Mg Grade 2# (CH) S-65C VHP (US) China has also large yielding capacity of Be and relevant experiences of neutron multiplier. China has built Be fabrication and manufactory in Ningxia Orient Nonferrous Metal Group Co. A new project, to develop high quality Be in China, is being implemented for ITER project. 34

35 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( Li 4 SiO 4, Li 2 TiO 3 ), are developing in China. Fabrication of the ceramic powder Fabrication sample of the Li 35 4 SiO 4 pebbles

36 Fabrication and Experiment of Ceramic Pebbles *** γ- LiAlO 2 Li 4 SiO 4 Diameter: 1~5mm Relative density:60~80%t.d. Crushing load:30~70n Diameter: 1mm Relative density: 90%T.D. Li 2 ZrO 3 Diameter: 1~5mm Relative density: 60~80%T.D. Crushing load: 30~70N *** Contribution from CAEP 36

37 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 : n/cm 2 sec; (E<0.625eV) Fast neutrons : n/cm 2 sec; (E>0.625eV) 235 U 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 37 (HFETR)

38 High Heat Flux Tests Optical pyrometer ( ) CCD View Electron-gun and pump system Measurement and control system Main parameters: Pressure: Pa (egun chamber), Pa (main chamber). Power: max. 3kW (60kV, 50mA). E-beam: Gaussian distribution, max. spot: ~φ20mm (ellipse). 38

39 HIP Technology development CuCrZr/316L-HIP weld module 850 o C/120MPa/3hr The technology is based on drilling holes and HIPing. Tensile strength is more than 260MPa. Cu/SS +SS tubes, 80x NDT method for flat interface of Cu-SS Supersonic wave detector 2. NDT method for the interface of Cu-SS tube 39

40 High Temperature He Experiment Loop A High Temperature He Experiment Loop (HTHEL)with 700 O C and 8-10 MPa, which is useful for HC-SB TBM design and R&D activities, is proposed to be built in SWIP. He Test Loop for HTGR Temp.: 900 O C, Total Power: 10MW Pressure: 3 MPa High Temperature He Experiment Loop 40

41 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 O C and 8-10 MPa (adjustable) SWIP/ Under construction A facility for high heat flux properties test High Flux Engineering Test Reactor (HFETR) Evaluation of plasma facing materials and components Max. power density: 20 MW/m 2, Active cooling, control of the temperature of coolant from RT- 150 Materials Test Thermal neutrons : n/cm 2 sec; (E<0.625eV) Fast neutrons : n/cm 2 sec; (E>0.625eV) SWIP/ Under construction 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) 41

42 Expected Collaboration on R&D Tritium technologies - Tritium extraction & purification - Tritium control and ISS - Tritium loop qualification - Tritium permeation barriers Ceramic breeder technologies - Fabrication; - Performance test; - Simulation and modeling; - 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.

43 IV. Summary Solid Breeder Blanket should be the basic option and first candidate in China. The progress and status of CH HC-SB TBM since 2004 are introduced briefly. Under the cooperation with domestic institutes, a update design description document (DDD) have been completed. The preliminary safety analysis reports will be submitted by the end of this year. Preliminary R&D program as well as the collaboration expected with other Parties are presented. Some key technologies are to be implemented, such as high temperature He experimental loop, Low-activation material (CLF), high qualified beryllium, HIP welding technology, optimized lithium ceramic breeder, etc. Relevant R&D on the key techniques are being preformed intensively and systematically with the cooperation of domestic and international institutions and companies. 43

44 Thank you for your attention! 44

45 21th IAEA FEC Conference will be hold in Chengdu International Conference Center, Oct.16-20,