A Brief Recount on Test Blankets (DEMO relevant blankets)

Transcription

1 A Brief Recount on Test Blankets (DEMO relevant blankets) Clement Wong Neil Morley Alice Ying Sergey Smolentsev Mohamed Abdou Mohamed Sawan Rick Kurtz Dai-Kai Sze Siegfried Malang General Atomics UCLA UCLA UCLA UCLA UW PNL UCSD Consultant FNST Meeting August 12-14, 2008, UCLA

2 Test blanket concepts follow the needs of DEMO US FUSION DEMO (Presented at the ITER TBWG-12, 2004) US Fusion DEMO is the last step before commercialization of fusion. Tritium self-sufficiency is a must*. All design criteria, safety requirements and environmental impacts and projections will have to be met. FW/blanket availability goal > 50% for a DEMO goal of >30%. General parameters: 2-4 MW/m 2 neutron wall loading, < 0.5-1* MW/m 2 surface loading, steady state operation and several hundred MW of electrical power. RAFS is the reference structural material. Breeder, coolant and design choices for the FW/blanket are open pending R&D and testing results in ITER and CTF. ITER serves a very important role in first integrated blanket testing in fusion environment. The tests are mainly Functional Tests. ITER tests are limited by short pulses, long dwell time, low fluence and partial coverage. CTF is considered essential in the US fusion development strategy to obtain data on: failure modes, effects and rates, approaching full coverage as well as on replacement time and availability with moderate to high neutron fluence. *Added or changed for this meeting

3 DEMO Compulsory Requirements Established by ITER Liquid Breeder TBM parties (Inherent requirements in test blanket design and selection) Thermal parameters and electric power at the level of commercial power reactor Tritium self sufficiency and 3-D TBR > 1.05 High reliability and satisfy operational safety requirements Decreased accidents consequences and waste disposal demands with respect to fission reactors Availability > 30 % Fusion Power Range: MW Optimize thermal efficiency

4 DEMO Relevant Blanket Concepts from the World Fusion Community Liquid breeder concepts from ITER TBM 1a. HCLL EU/C He cooled with circulating PbLi slowly for tritium extraction 1b. HCML Kor Similar to HCLL, but replace PbLi with Li 2. DCLL US/C Duel coolant, He and PbLi. Use of FCI PbLi operates at high T, allows high η th with FS 3. Li/V RF Li-self cooled with V-alloy, this has the simplest blanket configuration, but development of MHD insulation has not been successful Solid breeder concepts from ITER TBM 4. HCPB EU/others Helium cooled solid breeder 5. WCSB J Water-cooled solid breeder, can be cooled by pressurized or super critical water a concern Other advanced concepts: Most likely not suitable for DEMO 6. Recir-FLiBe US/J Recirculating FLiBe-self cooled to get higher FW velocity, using AFS, and Pb or Be as multiplier, Be as the REDOX agent. 7. SiC/PbLi US/EU SiC/SiC as structural material and PbLi as the coolant. SiC/SiC properties under high fusion neutron fluence uncertain 8. EVOLVE US W and vaporized Li as the heat removal coolant, W-alloy structural material not yet credible 9. W/Li/He US W and basically similar approach to HCLL, W-alloy structural material not yet credible

5 Different class of blanket concepts (At different levels of development) 1a. HCLL 1b. HCML 2. DCLL 3. Li/V 4. HCBP 6. Recir. FLiBe 7. SiC/PbLi 8. EVOLVE 9. W/Li/He 5. WCSB Advanced concepts

6 Advanced concepts have higher thermal performance (Mostly likely not ready in the next 50 years) Liquid breeder concepts from ITER TBM Γn, MW/m2 Struct. Mat Breeder Coolant TBR ηth, % 1a. HCLL 2.4 peak FS PbLi He (8 MPa) 1.15* ~35 1b. HCML > 2 FS/AFS Li He (8MPa) ~1.05 TBD 2. DCLL 3 peak FS PbLi He(8MPa)/PbLi (2MPa) 1.17* >40 3. Li/V > 2 V 4Cr 4Ti Li Li (1 Mpa) Solid breeder concepts from ITER TBM 4. HCPB 2.4 peak FS Li 4 SiO 4, (Li 2 TiO 3 ) He (8 MPa) WCSB 3.5/5 peak FS Li 2 TiO 3 or other SB Water (15/25 MPa) >1.05* 38.5/41.4 (PW/SCP) Other advanced concepts 6. Recir FLiBe 3.8/5.4 peak AFS (T limit: 800 C) FLiBe (MP 459 C) FLiBe (0.6 MPa) ~ SiC/PbLi 3.2/2 (Ave) SiC/SiC PbLi PbLi (1 MPa) EVOLVE 10 peak W alloy Li Boiling Li (0.037 MPa) 1.33 (local) W/Li/He 7 peak W alloy Li He (12MPa) 1.43 (local) 57.5 * 90% Li-6 enrichment

7 Required R&D are many, specifics and common, can be translated to $, 1of 3 1a 1b HCLL HCML DCLL Li/V HCBP/HCCB WCSB 1 FCI FCI development FCI...key 2 FCI radiated properties FCI key 3 MHD MHD insulator coating Critical 4 MHD insulator rad. properties Critical 5 Critical MHD effects, analysis and exp. MHD MHD 6 He He flow distribution He He He He 7 He FW heat transfer He He He He 8 He technology development He He He He He 9 CCGT system for He He 10 H2O Pressurized H2O system Pow Conv H2O 11 Materials FS Structural mat development FS FS FS FS FS 12 FS Structural mat rad properties FS FS FS FS FS 13 FS Struct. mat. components fab. FS FS FS FS FS 14 PFC materials Common Common Common Common Common Common 15 PFC mat. Joining & development Common Common Common common Common Common C piping materials key

8 Required R&D are many, specifics and common, can be translated to $, 2of 3 1a 1b HCLL HCML DCLL Li/V HCBP WCSB 17 Materials V Structural mat development V alloy 18 V Structural mat rad properties V alloy 19 V Struct. mat. components fab. V alloy 20 Material compatibility PbLi/FS > 500 C* May be O.K.** 21 Material compatibility PbLi/SiC May be O.K. 22 Pebble thermomechanical prop. CB CB 23 Be reaction with water Be & water 24 FS <350 C 300 C 25 CB beds char. and prod. CB CB 26 Be beds char. and production CB CB 27 CB, multi. beds Lifetime CB and Be CB and Be 28 Tritium Tritium inventory Common Common Common Common 29 LB Tritium permeation/control PbLi PbLi 30 Tritium extraction from PbLi PbLi PbLi 31 Tritium extraction from He He He He He 32 Tritium in Be Be Be 33 T recovery from water, scaleup H2O *Operating > 500 C, significant concern from erosion **Interface temperature controlled to < 480 C

9 Required R&D are many, specifics and common, can be translated to $, 3/3 1a 1b HCLL HCML DCLL Li/V HCBP/HCCB WCSB 34 Safety Design to off normal conditions Common Common Common Common Common Common 35 Availability Engr. Mat. Design data develop. Common Common Common Common Common Common 36 Components operation data Common Common Common Common Common Common 37 Small scale mock up tests Common Common Common Common Common Common 38 Medium scale mock up tests Common Common Common Common Common Common 39 Full size mock up tests Common Common Common Common Common Common 40 Integrated mockup tests Common Common Common Common Common Common 41 Integrated tokamak tests Common Common Common Common Common Common 42 E&M E&M analysis with SS and FS mix Common Common Common Common Common Common 43 MTTR Blanket installation and removal Common Common Common Common Common Common 44 Diagnostics Liq. Blanket diagnostics PbLi Li PbLi Li 45 Solid blanket diagnostics CB CB 46 Nuclear Nu data and modeling validation Common Common Common Common Common Common 47 Analytical Integrated analysis capability Common Common Common Common Common Common 48 Virtual blanket performance Common Common Common Common Common Common

10 Conclusions We (US and world blanket community) have studied and identified many acceptable blanket concepts It is obvious that we cannot develop all of them because of the large number of required R&Ds and correspondingly high total cost ITER TBM program will help to resolve common and specific R&D issues and up to fluence of 0.3 MW.yr/m 2 US selected DCLL and HCPB/HCCB concepts seem reasonable choices For the higher performance DCLL concept issues are FCI and critical MHD effects The backup for DCLL is HCLL