1 Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder Concept 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 3 rd PRC/US MCF Collaboration workshop – Dalian, China, May 18-19, 2006`1

2 Outline I.Introduction II.Design Progress III.Performance Analysis IV.R&D and Test Plans V.Possible Collaborations VI.Summary

3 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 China’s DEMO definition and development strategy. The preliminary design and analysis of HC-SB TBM have been carried out recently. Possible collaborations on TBM R&D with other partiers have been proposed. I. Introduction

4 ITER,TBM and DEMO

5 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.

6 Two options of breeding blanket with ceramic and lead lithium- lead breeders might be chosen as China’s DEMO blanket concepts under the conditions of meeting the requirement of the neutronics, thermo-hydraulics and mechanics aspects. Selection of DEMO Blanket HC-SB DEMO Blanket(SWIP) DCLL DEMO Blanket(ASIPP)

7 Selected HCSB DEMO Parameters Chinese HC-SB DemoParameters Fusion power/electric power (MW)2000 / ~ 600MWe Major radius (m)7.0m Minor radius (m)2.5m Neutron wall load (MW/m 2 )~ 2.0 Surface heating (MW/m 2 )~0.3 Tritium breeding ratio (TBR)>1.1 Availability (%)50-70 Divertor peak load (MW.a/m 2 )8.0 (water-cooled) Plasma operation modeContinuous

HC-SB DEMO Blanket Design

9 II. Design progress of CH HC-SB EM-TBM

10 It is in agreement with other parties’s design, HC-SB TBM design is based on a vertical half-port space in test Port C; 630mm(d) X 660mm(w) X 890mm(h ) Test Port Space for CH HC-SB TBM HCS TWCS HC-SB EM- TBM (I) HC-SB EM- TBM (II) Port C HC-SB TBM

11 Originally Design of CH HC-SB TBM （ 2004 Version ）

12 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 HC-SB TBM design Be Solid Breeder Back-plane He

13 Exploded 3-D view of Modified Design of HC-SB TBM (2005 Version) Structure and components design in detail is on going.

14 Structure Design for EM-TBN Be armor: 2 mm Max Temp. 514 O C First wall thickness: 30 mm Material: Eurofer Max T: 506 O C Cooling tube: 18x14.5mm Unit cells: 3X3 sub-modules He pressure: 8 MPa 664mm Integration view of structure design Sub-modules m in toroidal m in radial m in poloidal 664mm 890mm 630mm

15 Schematic view of CH HC-SB EM-TBM Outside of structure Cross-section of module Coolant manifold Sub-module structureView of the back-plane Configuration of Sub-modules

16 Connection of Up-down Modules HC Pipe (outlet) HC Pipe (inlet) Connection Modularizing structure Parallel connecting two modules Up module Down module

17 Connection of Components FW attachment TBM in ITER frame Flow path of coolant

18 Structure View of Back-plane He outlet Purge outlet Measure Channel Purge inlet He inlet Purge Collection manifold Purge Supply manifold He Supply manifold He Collection manifold He Middle manifold 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 Arrangement of back-plane Top view of manifold

19 Assembly of HC-SB EM-TBM in frame TBM module Frame

20 HCSB TBM integrated assembly

21 ItemsNT-TBMEM-TBM ConfigurationBOT (Breeder Out of Tube)Modules: 3×3 Sub-modules First wall area Neutron wall loading Surface heat flux m(W)×0.890 m(H)0.591 m MW/m MW/m 2 (normal condition) 0.5 MW/m 2 (extreme condition) m m 2 (Vertical) MW/m 2 (normal condition) 0.3 MW/m 2 (extreme condition) Total heat depositionsurface heat flux included0.76 MW0.177 MW Globe TBRLithium orthosilicate, Li 4 SiO (1-D), 80% Li-6 Tritium production rateITER operation condition2.23 ×10 -2 g/d Sub-module dimension(P)× (T) × (R)260 mm×190 mm×420 mm Ceramic breeder (Li 4 SiO 4 ) Two size Thickness Max. Temperature Diameter: 0.5~1 mm, pebble bed 90 mm (four zones) 737 ℃ SiC pebble bed, 0.5~1 mm Neutron multiplier (Beryllium) Two size Thickness Max. Temperature Diameter: 0.5~1 mm, Pebble bed 200 mm(five zones) 617 ℃ Al pebble bed, 0.5~1 mm Be armorThickness Max. Temperature 2mm 543 ℃ 2mm 514 ℃ Structure MaterialFerritic 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 MPa 300/500 ℃ 0.73 kg/s 85/80 mm 8 Mpa MPa 300/411 ℃ 0.31 kg/s 85/80 mm He purge flow (He)Pressure Pressure drop 0.12 MPa 0.02 MPa Design parameters for the HC-SB TBM

22 Schematic views of Coolant flow Coolant flow in the sub-module Coolant flow in FW Back-plate Coolant Flow Direction Back-plate

23 HC-SB TBM Auxiliary System HC-SB TBM HC-SB TBM HCS CPS VVPort CellTWCS vault Tritium Building BC TES TMS NMS

24 HC-SB TBM Auxiliary Sub-system Design HCSTMSTES CPSNMS TCWS

25 Neutronics Measurement System Design Schematic diagram of neutron fluxes and spectra measurement system and cooling loop for NT-TBM micro-fission chamber micro-fission chamber assembly

26 Iii. Performance Analysis for EM-TBM

27 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

28 Performance Analysis for HC-SB TBM (Con’t) Calculation Model Temperature on Flow Channel Flow scheme Temperature distributionThe displacement vector sum The stress distribution Peak stress is 63.5 MPa

[1].Temperature at FW outlet is fixed at C for test of high temperature performance of FW. Components Normal conditionExtreme condition EM-TBMNT-TBMEM-TBMNT-TBM Neutron surface loading [MW/m 2 ] Surface heat flux [MW/m 2 ] Helium pressure [MPa]8888 Helium inlet/outlet temperature [°C]300/411300/500300/411300/500 Total power (surface heat flux included) [MW] Power from surface heat flux [MW] Power from nuclear heating [MW] Total Mass flow rate of helium [kg/s] Mass flow rate of helium in FW [kg/s] Single sub-module [kg/s] Top and bottom plates [kg/s] Velocity of helium in FW [m/s] Sub-module [m/s] Pressure drop of coolant in module [MPa] Pressure drop in FW [MPa] Pressure drop in sub-module [MPa] Main Design Parameters of HC-SB EM-TBM[1]

[2]. Coolant velocity in FW outlet is fixed at 69m/s, to test the hydromechanics performance of FW channel. Components Normal conditionExtreme condition EM-TBMNT-TBMEM-TBMNT-TBM Neutron surface loading [MW/m 2 ] Surface heat flux [MW/m 2 ] Helium pressure [MPa]8888 Helium inlet/outlet temperature [°C]300/ /500300/341300/500 Total power (surface heat flux included) [MW] Power from surface heat flux [MW] Power from nuclear heating [MW] Total Mass flow rate of helium [kg/s] Mass flow rate of helium in FW [kg/s] Single sub-module [kg/s] Top and bottom plates [kg/s] Velocity of helium in FW [m/s] Sub-module [m/s] Pressure drop of coolant in module [MPa] Pressure drop in FW [MPa] Pressure drop in sub-module [MPa] Main Design Parameters of HC-SB EM-TBM (con’t)[2]

31 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;

32 Safety Analysis (con’t) Activation & afterheatReliability analysisE-M calculation model E-M analyses LOCA analysesLOFA analyses

33 VI. Test and R&D plans

34 Relevant R&D plans System Integration, Out-pile R&D Module fabrication technology Thermo-mechanical integrity of module Thermo-mechanical performance Thermal hydraulic research System Integration, Out-pile R&D Module fabrication technology Thermo-mechanical integrity of module Thermo-mechanical performance Thermal hydraulic research In-pile R&D Breeder/multiplier development Irradiation technology development Irradiation tests of blanket partial mockup In-pile R&D 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 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 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. Material Development Irradiation data of RAFM (CLAM), etc. Environmental effect, etc.

35 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 : 6.2×10 14 n/cm 2 sec; (E<0.625eV) Fast neutrons : 1.7 ×10 15 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 (HFETR)

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

37 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 sample of the Li 4 SiO 4 pebbles Fabrication of the ceramic powder

38 General Design and R&D Schedule for HC-SB TBM Items Day 1 Design Phase Detail design Engineering design Materials Development Ceramic Breeder, Li 4 SiO 4, Li 2 TiO 3 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

39 Years 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 Time Schedule for CH HC-SB TBM Fabrication and Test

40 Proposed test facilities prior to TBMs installation in ITER Facilities nameMain objectivesParametersLocation A high temperature He Experiment Loop based on China HTGR technologies. TBM mock-ups test O C 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/m 2, Active cooling, control of the temperature of coolant from RT- 150 SWIP/ (planning) High Flux Engineering Test Reactor (HFETR) Materials TestThermal neutrons : 6.2×10 14 n/cm 2 sec; (E<0.625eV) Fast neutrons : 1.7 ×10 15 n/cm 2 sec; (E>0.625eV) CINP/ (existing) Facilities of tritium extraction, purification, permeation, and test Tritium extraction and recovery experiment from the purge gas and coolant. TBDCAEP, CIAE & SWIP (planning)

41 1. CH TBM Projects 1.1 Test Blanket Module QA Management Safety & Licensing Safety & Licensing Test Plane Management Test Plane Management Design 1.2 Ancillary System 1.3 Project Strategy Testing Relevant R&D Testing Relevant R&D Performance Analysis Performance Analysis Prototype Fabrication & Testing Prototype Fabrication & Testing TBM Fabrication & Assembly TBM Fabrication & Assembly Design, R&D HCS TES CPS MS Fabrication & Assembly Fabrication & Assembly TBM integration installation TBM integration installation Technology Relevant R&D Technology Relevant R&D Testing integration Performance Testing integration Performance Work Breakdown Structure of HC-SB TBM..\..\WBS 系统 \WBS( ).xls

 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. Expected Collaboration on TBM R&D

43 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) TUNET Tinghua Uni, Institute of Nucl. Energy Tech. (HCS) TUNET Tinghua Uni, Institute of Nucl. Energy Tech. (HCS) CAEP China Academy of Engineering Physics (CPS, TES) CAEP China Academy of Engineering Physics (CPS, TES) Ningxia Orient Non-ferrous Metal Group CO.,LTD Be pebbles

44 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 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.

45 Thank you for your attention!