SABR FUEL CYCLE C. M. Sommer, W. M. Stacey, B

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SABR FUEL CYCLE C. M. Sommer, W. M. Stacey, B SABR FUEL CYCLE C. M. Sommer, W. M. Stacey, B.Petrovic, Georgia Tech September, 2009 Promise of FFH transmutation reactors: Longer fuel residence time limited by radiation damage, not criticality. Larger TRU fuel fraction, not limited by TRU β.

SUB-CRITICAL ADVANCED BURNER REACTOR (SABR) ANNULAR FAST REACTOR 1. Fuel—TRU from spent nuclear fuel. TRU-Zr metal being developed by ANL. 2. Sodium cooled, loop-type fast reactor. Based on fast reactor designs being developed by ANL in DoE Nuclear Program. TOKAMAK D-T FUSION NEUTRON SOURCE 1. Based on ITER plasma physics and fusion technology. 2. Tritium self-sufficient (Li4SiO4). 3. Sodium cooled.

R-Z Cross section SABR calculation model

FUEL Axial View of Fuel Pin Composition 40Zr-10Am-10Np-40Pu (w/o) LiNbO3 t=0.3 mm ODS Clad t=0.5 mm Na Gap t=0.83 mm Fuel R=2 mm FUEL Axial View of Fuel Pin Composition 40Zr-10Am-10Np-40Pu (w/o) (Under development at ANL) Design Parameters of Fuel Pin and Assembly Length rods (m) 3.2 Total pins in core 248778 Length of fuel material (m) 2 Diameter_Flats (cm) 15.5 Length of plenum (m) 1 Diameter_Points (cm) 17.9 Length of reflector (m) 0.2 Length of Side (cm) 8.95 Radius of fuel material (mm) Pitch (mm) 9.41 Thickness of clad (mm) 0.5 Pitch-to-Diameter ratio 1.3 Thickness of Na gap (mm) 0.83 Total Assemblies 918 Thickness of LiNbO3 (mm) 0.3 Pins per Assembly 271 Radius Rod w/clad (mm) 3.63 Flow Tube Thickness (mm) Mass of fuel material per rod (g) 241 Wire Wrap Diameter (mm) 2.24 VolumePlenum / Volumefm Coolant Flow Area/ assy (cm2) 75 Cross-Sectional View Fuel Assembly

NEUTRONICS ERANOS fast reactor fuel cycle code JEFFF2.0 cross-sections, 20 MeV-0.1eV P1 lattice cell calculation, 1968 groups, collapsed to 33 groups and homogenized over assembly. 2D RZ model, 91 radial and 94 axial mesh points,S-8.

FUEL CYCLE 4-batch, out-to-in fuel shuffle Burn cycle 700 FPD Fuel residence time (4 burn cycles) set by 200 dpa limit on ODS steel clad and structure. Unavailability during burn cycle-- 10%. Refueling downtime between burn cycles-- 60 days. TRU reprocessing—pyrometallurgical (ANL) TRU fuel fabrication—arc casting (ANL) 99% separation efficiency for—1% TRU with fission products to geological repository, 1% fp with TRU to fuel fabrication.

Reprocessing Facility FUEL CYCLE Reprocessing Facility # burn cycles fuel has been in reactor at BOC 1 2 3 4 Fuel Assembly numbers Fuel Fabrication Facility Plasma

4-BATCH FUEL CYCLE Fuel cycle constrained by 200 dpa clad radiation damage lifetime. 4 (700 FPD) burn cycles per residence OUT-to-IN fuel shuffling BOL keff = 0.972, Pfus = 75MW, 32 MT TRU BOC keff = 0.894, Pfus = 240MW, 29 MT TRU EOC keff = 0.868, Pfus = 370MW, 27 MT TRU 24% TRU burnup per 4-batch residence, >90% with repeated recycling 1.05 MT TRU/FPY fissioned Supports 3.5 1000 MWe LWRs (0.25 MT TRU/yr) at 84% availability. SABR TRU FUEL COMPOSITION (w/o) Isotope Fresh Fuel To Process Core Av EOC/BOC Np-237 17.0 7.25 9.1/8.3 Pu-238 1.4 17.3 14.6/17.3 Pu-239 38.3 18.3 21.9/20.3 Pu-240 29.2 27.2/28.2 Pu-241 6.5 7.31 5.55/5.55 Pu-242 2.6 7.45 6.50/6.99 Am-241 13.63 8.87/8.35 Am-42m 0.00 0.84 0.71/0.74 Am-243 2.8 2.79 2.82/2.85 Cm-242 0.59 0.33/0.35 Cm-243 0.10 .075/.080 Cm-244 2.51 2.01/2.24 Cm-245 0.56 0.42/0.49 ANNULAR CORE CONFIGURATION

GENERAL COMMENTS SABR could operate on other reprocessing fuel cycles (e.g. burn MAs after TRU pre-burned in critical burners and/or as MOX in LWRs). The SABR neutron source could be used with other types of reactors (e.g.the GCFTR design used TRISO fuel in gas-cooled fast reactors on a “burn and bury” fuel cycle). With reprocessing fuel cycles the issues are i) the separation efficiency and ii) the number of reprocessing steps. With the “burn and bury” fuel cycles the issues are i) the radiation damage limit and ii) criticality. The FFH can ameliorate the second issue for both fuel cycles.