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Current Status of Solid Breeder TBM in China

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.

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Current Status of Solid Breeder TBM in China

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  1. 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

  2. OUTLINE 1. Introduction 2. Progress on Updated Design 3. Progress on Relevant R&D 4. Test Plan and Cooperation 5. Summary

  3. 1. Introduction • ITER is an unique opportunity to test tritium breeding blanket mock-ups in an integrated tokamak operating conditions; • Helium-cooled ceramicbreeder (HCCB) test blanket module will be the primary optionof 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.

  4. 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 Fusion Breeder? 2010 2020 2035 2050

  5. 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. HC-SB DEMO Blanket

  6. TBM Concepts and Port-Sharing Six TBM Systems to be installed in ITER in different operation phases 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

  7. 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.

  8. 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 Cross-section of SB Integration View of CN HCSB TBM Assembly scheme of Sub-Modules

  9. Updated Design of HCCB TBM for Reduction RAFM Mass • Objectives of updated design: • - to simplify Sub-module structure; • - toreduce 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. Cross-section of SM HCCB TBM Module TBM Sub-module arrangement • Main modification • 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. Exploded view of sub-module

  10. Performance Analyses for Updated TBM Design Tmax= 517 OC Tmax= 548 OC Tmax= 621 OC b) Be pebble bed c) Li4SiO4 pebble bed d)Sub-module a) RAFM material Temperature Distribution of Sub-module • Main calculation results Temperature and stress distribution of FW • Main parameters meet design requirement. • TPR is obviously increased.

  11. Performance Analyses for Updated TBM Design Thermal analysis thermal analysis model Primary stress Secondary stress Thermal analysis results of sub-module Stress analysis

  12. CN HCCB TBM Auxiliary Sub-system Design

  13. Design Parameters for the HCCB TBM

  14. CN TBS Integration with ITER (Con’t) 2 half-ports C5 CN-HCCB C6 IN-LLCB View of Pipe Forest and TBM-Sets in Port #2

  15. CN TBS Integration with ITER Tokamak Coolant Water System vault India part Port Cell area Port Cell (AEU) Interspace (Pipe forest) Port 2# (Port Plug) L2 of Tritium building for TES China part • 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. Interface 3 Interface 1 Interface 2a Interface 2b Space Arrangement Identification of CN TBS Space arrangement

  16. 3. Progress on R&D:Structural Materials-CLF-1 • Two RAFM alloys are being developed in China; CLF and CLAM • A 500kg and 1-ton ingots of CLF-1 steel were recently produced byvacuum induction melting and electro-slag remelting method. • The optimization of the melting technique forthe larger ingots to is underway. Consumable electrode furnace Remelting facility 1-ton Ingot of CLF-1 Tensile strength of CLF-1 DBTT of CLF-1 500kg Ingot of CLF-1

  17. 3. Progress on R&D:Ceramic Breeder Pebbles • 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. • 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) ; • Li2TiO3Pebbles have good surface feature by using sol-gel method. XRD pattern of Li4SiO4 pebbles Li4SiO4 Pebbles (D=1mm) by metl spraying method @SWIP Li4SiO4 Pebbles (D=1mm) by freeze-sintering method @CAEP Main properties (Li4SiO4) by melt spraying method Li4SiO4 Pebbles (D=1mm) by extrusion–sintering method @CIAE Li2TiO3 Pebbles (D=1mm)@CAEP

  18. 3. Progress on R&D:Fabrication of Be Pebbles Main chemical composition of Chinese Be 1# • 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 Pebbles (D=1mm) Sample of Be Pebbles(D=1mm) Micrographs of Be Pebbles (D=1mm) REP Facility at HBSM Co.

  19. 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 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. Layout of He Loop Cross-section view Flow diagram of He Loop

  20. 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 High flux test reactor • 3. EM-TBM will be installed in ITER port after the first plasma shutdown (2019) 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)

  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 Safe & QA Team Design Team R&D Team SWIP CAEP CIAE ASIPP XJTU NCEPU NCIRD IMPCAS NPIC TUINET SICCAS SJTU SWIP CAEP CIAE SJTU ASIPP NCEPU XJTU IMPCAS NPIC TUINET SICCAS HBSMC SWIP CAEP CIAE NCEPU ASIPP TUINET NPIC TUINET NCIRD 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; SICCAS: Shanghai Institute of Ceramics, Chinese Academy of Sciences ; HBSMC: Haibao special metal materials Co.

  25. 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.

  26. 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.

  27. Thanks for your Attention !

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