ML22336A107

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M221208: Slides/Supporting Presentation Material - J. Vollmer - Overview of Advanced Reactor Fuel Activities
ML22336A107
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Issue date: 12/08/2022
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NRC/OCM
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ML22293A445 List:
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M221208
Download: ML22336A107 (6)


Text

Development and Qualification of Advanced Fuel Designs for the Natrium'*

and Molten Chloride Fast Reactor Designs

James Vollmer Senior Manager, Fuel Development & Qualification

  • A Te r ra Po w e r & GE-Hitachi Technology

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0008924 Copyright© 2022 TerraPower, LLC. All Rights Reserved.

Fuel Development and Qualification Effor ts

  • Since our inception in 2008 TerraPower has actively been working on advancing fuel designs including metallic fuels for the Traveling Wave Reactor (T WR) 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 effor t was funded by the Depar tment of Energy through a regulator y assistance grant to help TerraPower refine our approach for metallic fuel qualification by suppor ting early engagement with the NRC (ML20209A155, ML20316A038, ML21057A008)
  • Four total documents prepared as par t of this effor t:

- 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)

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0008924 2 Copyright© 2022 TerraPower, LLC. All Rights Reserved.

Advancing Metallic Fuel Designs

Fuel Pin Cross-Sections Pins Arranged in Hexagonal U-10Zr 75% Smear Density Assembly Surrounded by a Duct EBR-II* Cladding (Mk IV) Fuel 5.84mm Bond Sodium FFTF*

(MFF) 6.86mm

Host Fuel (Type 1)

>6.86mm Commercial He-filled Advanced Central Pore Fuel-Cladding Fuel (Type 1B) Chemical *EBR-II: Experimental Breeder Reactor II Interaction Barrier *FFTF: Fast-Flux Test Facility Comparison of Fuel Assembly Heights

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 3 Copyright© 2022 TerraPower, LLC. All Rights Reserved.

Natrium Fuel Qualification Path

Type 1/Host Fuel Activities

Qualification of Po st-Irradiation Exams Irradiation Test Transient Testing of Existing EBR-II Fuel on Historic FFTF/MFF Comparing Historic Irradiated FFTF/MFF Natrium Reactor Data Pins and New Na-Bonded Pins Fuels

Type 1B/Advanced Fuel Activities

Advanced Test Reactor Transient Testing of Fresh Lead Test Assembly Commercial Natrium (ATR) Tests of Type 1B and Irradiated Advanced Testing of Advanced Fuels Reactors Fuel Fuel Pins in Natrium Reactor

Host and Advanced Fuel Testing Activities Being Performed in Parallel

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 4 Copyright© 2022 TerraPower, LLC. All Rights Reserved.

Natrium Program Roadmap

Commercial Series II+

Natrium (Up to GWe scale)

Natrium Commercial Series I Commercial Series I Benefits Plant (345 MWe 500 MWe) +Depleted Uranium (345 MWe 500 MWe) Breed-and-Burn 3 yr. Construction +Potential Used Nuclear Fuel U.S. legacy sodium-cooled fast Commercial Plant Economics +Energy Storage & Peaking Recycling reactor experience, PRISM and +Energy Storage & Peaking Capability Capability +Potential Pu Disposition TWR development +Zero-Carbon Process Heat 1980s-2019 2021-20282028-2030s~2040s

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054Copyright© 2022 TerraPower, LLC. All Rights Reserved.

Copyright© 2022 TerraPower, LLC. All Rights Reserved. 5

= non-nuclear facility MCFR Technology = nuclear reactor/facility Development Roadmap MCFR Grid-Scale MCFR Pu Product Burner 350-1200 MWe Prototype MCFR Demo 10 MWt Reactor

(MCFR-D)

Molten 30- 180 MWt Integrated Chloride Effects Test Reactor (IET) Experiment Component Facility 150 kWt Test Facility MCFR Small-to-Mid Scale Product 30-300 MWe Separate Effects Tests (SETs) (w/o component scale-up)

2016 - 2026 2026 - 2031 2030s

SUBJECT TO DOE COOPERATIVE AGREEMENT NO. DE-NE0009054 6 Copyright© 2022 TerraPower, LLC. All Rights Reserved.