ML22336A107
| ML22336A107 | |
| Person / Time | |
|---|---|
| Issue date: | 12/08/2022 |
| From: | NRC/OCM |
| To: | |
| Shared Package | |
| ML22293A445 | List: |
| References | |
| M221208 | |
| Download: ML22336A107 (6) | |
Text
SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0008924 Copyright© 2022 TerraPower, LLC. All Rights Reserved.
Development and Qualification of Advanced Fuel Designs for the Natrium'*
and Molten Chloride Fast Reactor Designs James Vollmer Senior Manager, Fuel Development & Qualification
- A TerraPower & GE-Hitachi Technology
Fuel Development and Qualification Efforts Since our inception in 2008 TerraPower has actively been working on advancing fuel designs including metallic fuels for the Traveling Wave Reactor (TWR) and Natrium reactor designs and molten salt fuels for the Molten Chloride Fast Reactor (MCFR) designs Active engagement with the NRC to advance our fuel qualification strategies Advanced Fuel Qualification Methodology effort was funded by the Department of Energy through a regulatory assistance grant to help TerraPower refine our approach for metallic fuel qualification by supporting early engagement with the NRC (ML20209A155, ML20316A038, ML21057A008)
Four total documents prepared as part of this effort:
- 1) Overall fuel qualification methodology, 2) Fuel Assembly Qualification Plan, 3) Type 1 Fuel Pin Qualification Plan (host fuel), and 4) Type 1B Fuel Pin Qualification Plan (advanced fuel) 2 SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0008924 Copyright© 2022 TerraPower, LLC. All Rights Reserved.
Advancing Metallic Fuel Designs EBR-II*
(Mk IV) 5.84mm FFTF*
(MFF) 6.86mm Commercial Advanced Fuel (Type 1B)
Fuel Bond Sodium Host Fuel (Type 1)
>6.86mm U-10Zr 75% Smear Density Fuel-Cladding Chemical Interaction Barrier Cladding He-filled Central Pore Fuel Pin Cross-Sections Pins Arranged in Hexagonal Assembly Surrounded by a Duct Comparison of Fuel Assembly Heights 3
SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 Copyright© 2022 TerraPower, LLC. All Rights Reserved.
- EBR-II: Experimental Breeder Reactor II
- FFTF: Fast-Flux Test Facility
4 Natrium Fuel Qualification Path Qualification of Existing EBR-II Fuel Data Post-Irradiation Exams on Historic FFTF/MFF Pins Irradiation Test Comparing Historic and New Na-Bonded Fuels Transient Testing of Irradiated FFTF/MFF Pins Natrium Reactor Advanced Test Reactor (ATR) Tests of Type 1B Fuel Transient Testing of Fresh and Irradiated Advanced Fuel Pins Lead Test Assembly Testing of Advanced Fuels in Natrium Reactor Commercial Natrium Reactors Type 1/Host Fuel Activities Type 1B/Advanced Fuel Activities Host and Advanced Fuel Testing Activities Being Performed in Parallel SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 Copyright© 2022 TerraPower, LLC. All Rights Reserved.
Copyright© 2022 TerraPower, LLC. All Rights Reserved.
Natrium Program Roadmap U.S. legacy sodium-cooled fast reactor experience, PRISM and TWR development Commercial Series II+
(Up to GWe scale)
Commercial Series I Benefits
+Depleted Uranium Breed-and-Burn
+Potential Used Nuclear Fuel Recycling
+Potential Pu Disposition
+Zero-Carbon Process Heat Natrium Plant (345 MWe 500 MWe)
Commercial Plant Economics
+Energy Storage & Peaking Capability Natrium Commercial Series I (345 MWe 500 MWe) 3 yr. Construction
+Energy Storage & Peaking Capability 1980s-2019 2021-2028 2028-2030s
~2040s SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 Copyright© 2022 TerraPower, LLC. All Rights Reserved.
5
MCFR Technology Development Roadmap Component Test Facility MCFR Grid-Scale Product 350-1200 MWe MCFR Small-to-Mid Scale Product 30-300 MWe (w/o component scale-up)
MCFR Demo Reactor (MCFR-D)30-180 MWt Integrated Effects Test (IET)
Facility
= non-nuclear facility
= nuclear reactor/facility 2016 - 2026 2026 - 2031 2030s Separate Effects Tests (SETs)
MCFR Pu Burner Prototype 10 MWt Molten Chloride Reactor Experiment 150 kWt 6
SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 Copyright© 2022 TerraPower, LLC. All Rights Reserved.