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Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers L. El-Guebaly and the ARIES Team Fusion Technology Institute University.

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Presentation on theme: "Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers L. El-Guebaly and the ARIES Team Fusion Technology Institute University."— Presentation transcript:

1 Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers L. El-Guebaly and the ARIES Team Fusion Technology Institute University of Wisconsin - Madison 16 th TOFE Meeting September 14-16, 2004 Madison, WI

2 Develop design space and operational windows for ARIES-IFE-HIB (no point design). Concerns: –Breeding potential of candidate breeders: Flibe & Flinabe –Ability of liquid wall to protect structure for 40 FPY –Activation level of structural components: shield & nozzles –Isochoric heating problems –Effect of radiation damage and cyclic fatigue on structure lifetime. Objectives

3 Schematic of Radial Build Flibe (BeF 2,(LiF) 2 ) and Flinabe (NaF, LiF, BeF 2 ) with natural Li. ODS FS (preferred structure) or 304-SS. Innermost layer of shield represents nozzles and feeding tubes. Point source and 1-D spherical geometry. FS Shield (90% FS, 10% Liquid) Gap Target Liquid Blanket Jets (58% Liquid, 42% void) 0.5 m Radius 3 m Radius | | | Nozzles |

4 Target yield 460 MJ Rep rate4 Hz # of pulses126 million/FPY Average source neutron energy11.8 MeV Penetrations coverage3% Plant lifetime 40 FPY Availability85% Key ARIES-IFE-HIB Parameters

5 Overall TBR≥ 1.08 dpa* to structure ≤ 200 dpa for FS ≤ 25 dpa for 304-SS He production for reweldability of FS≤ 1 He appm WDR for Class C low level waste≤ 1 ___________________ * Cyclic fatigue could be more restrictive life-limiting factor than radiation damage. ARIES-IFE Requirements and Design Limits

6 85 cm thick Flibe and 150 cm thick Flinabe meet breeding requirement. Enrichment does not enhance breeding of thick Flinabe. Nuclear energy multiplication amounts to ~1.25. Flibe Breeds more Tritium than Flinabe

7 85 cm Flibe blanket meets 200 dpa limit for advanced FS only. 1.5 m Flinabe meets dpa limits for both structures. Flibe has Slightly Better Shielding Performance than Flinabe

8 Problem: Innermost layer of shield and nozzles cannot be rewelded at any time during operation. Excessive Helium Production at Chamber Structure

9 ODS M-F82H-FS * 304-SS # Fe 87.891 70.578 C0.040.046 N0.0050.038 O0.13– Si0.240.47 P0.0050.026 S0.0020.012 Ti0.090.03 V0.29– Cr8.717.7 Mn0.451.17 Co0.00280.1 Ni0.04749.3 Cu0.010.2 Nb0.00033– Mo0.00210.33 Ta0.08– W2– Y0.7– _____________________________________________________ * IEA Modified F82H FS + 0.25wt% Y 2 O 3, per M. Billone (ANL). Other elements include: B, Al, As, Pd, Ag, Cd, Sn, Sb, Os, Ir, Bi, Eu, Tb, Dy, Ho, Er, U. # C. Baker et al., "Starfire-A Commercial Tokamak Fusion Power Plant Study," Argonne National Laboratory Report, ANL/FPP-80-1 (1980). Steel Composition (in wt%)

10 304-SS generates very high level waste. Main contributors to WDR: 94 Nb (from Nb), 99 Tc (from Mo), and 192n Ir (from W). All Steel Alloys Generate High Level Waste Flibe System Flinabe System

11 –Thicken blanket and deplete Flibe/Flinabe (cost?), –Average WDR over thicker shield (> 50 cm), –Control Mo and Nb for Flibe system in particular (cost?). In practice, Mo and Nb impurities cannot be zeroed out. Actual level depends on $/kg to keep Mo and Nb << 1 wppm. Nozzles generate high level waste unless mixed with shield and disposed as single unit at end of life. Potential Solutions for Waste Problem

12 FS temperature fluctuates 4 times per second. Nuclear heating will induce stresses on the order of 10 MPa in FS Fatigue from cycling and repetitive shock wave could: –Cause internal cracks –Shorten structure life When combined with radiation damage, fatigue life could be more restrictive than 200 dpa limit. Isochoric Heating 0.25 s

13 Concluding Remarks No breeding problem identified for Flibe and Flinabe. Excessive helium production at structure precluding FS reweldability during operation. Steel-based structure produces high level waste (WDR >> 1), mandating: – Thicker blanket with depleted lithium (cost ?) – Shield > 50 cm thick, and/or – Nb and Mo impurity control (cost?). Nozzles need additional protection to qualify as low level waste unless mixed and disposed with shield. Combined effect of radiation damage and fatigue on structure lifetime should be addressed in future studies.

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