·framatome
AGENDA
• Introduction and background
• Failure Modes & Effects Analysis and Design Review Summary
• Test program
• Models • Topical Repo_rt outline
• Next steps
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-Introduction and Background
EATF Solution Cr-Coated Cladding / Chromia-doped Pellets
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Base M5 Cladding • No change to MS properties or
dimensions
Cr-coating • 10-20 µm
• Does not change base MS
• Improved oxidation resistance
• Improved wear resistance
• Reduced LOCA rupture
Chromia-doped U02 pellets
• BWR licensing approved
• Improved fission gas retention
• Improved fragmentation behavior
• Improved PCI performance
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Overview of Plan
• Base Topical Reports for Advanced Methods
• ANP-10323P, Revision 1, "GALILEO Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactors"·
• ANP-10339P, "ARITA-ARCADIA/RELAP .Integrated Transient Analysis Methodology"
• BAW-10227P, Revision 2, "Evaluation of Advanced Cladding and Structural Material (MS) in PWR Reactor Fuel"
• Topical report for implementation of GALILEO in W&CE LOCA methodologies (SBLOCA and RLBLOCA)
• · Extension to Advanced Products (Cr-Cr EATF Solution)
• Chromia-doped pellet topical report supplement (ANP-10340P) report to extend material properties to PWR methodologies
• BAW-10227 supplement to incorporate chromium-coated cladding (addressing base methods)
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Advanced Products - EATF Cr-Coated. Cladding Topical_ Report
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Purpose _ ~ . • Implement Chromium coated cladding properties into PWR codes and
methods · - _ · . • Supplement to BAW-10227P, Revision 2
Scope Detail • Chromium coated M5 cladding
• Define new properties / models for Cr-coated cladding • Disposition MS properties where applicable
~ Implementation of Cr-coated cladding in • GALILEO -• LOCA Methodologies • ARITA/ AREA Methodologies
• Address failure mechanisms and surveillance plans • Appropriate sample problems for Cr-coated cladding addressed /
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. . Background
• BAW-10227PA, Revision O appro.ved February 2000
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BAW-10227PA, Revision 1 approved June 2003 • Extended burnup to 62 GWd/mtU
BAW-10227, Supplement 1 P "Evaluation of Advanced Cladding and Structural Material (MS) in PWR Reactor Fuel". • Extend the range of applicability of models and correlations .. Submitted May 20.17 .
BAW-10227, Revision 2 "Evaluation of Advanced Cladding and Structural Material (MS) in PWR Reactor Fuel" · • Update ofMS properties l_
BAW-10227, Supplement 2P "Incorporation of Chromium Coated Cladding Properties . .
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Recent Results
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Beginning of Proprietary Information
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Recent Results - Corrosion
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Recent Results - Beyond Eutectic Temperature
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Failure Modes & Effe.cts Analysis and -Design Review
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FMEA
• Objective: Identify all possible risks of failures in a design • Conducted on October 16th, 2018 per US Fuel administrative procedure
• Risk Priority Number (RPN) rankings were determined for each Failure Mode based on Severity , Occurrence and Detection • Final RPN could range from 1 to 1000 • 1 is very low risk and 1000 is high risk
• Team identified [ ]
5 FMEA exercise yielded RPNs ranging from [ ]
Cross-functional team: -
Materials, . Thermal-Mechanics, Fuel Reliability,
Neutronics, Thermal-Hydraulics, LOCA!non-LOCA,
Severe Accident, Mechanical Design,
· Radiological,
Regulatory Affairs, RCS Chemistry, RIA
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Design Review
• Objective: Review the technical status of Cr-coated cladding and ensure all the · requirements and constraints are completely identifi~d
• Conducted on November 13th, 2018 per US Fuel administrative procedure
• Bounding Assumptions • Coating and Manufacturing processes will produce cladding which meets the design
requirements . [ ]
• Industrialization aspects, contractual needs, etc. are out of scope of this design review
• Board made [ 1-Materials, Neutronics,- Severe Accident, · Regulatory Affairs, Physical Vapor
Cross-functional Thermal-Mechanics, Thermal-Hydraulics, Mechanical Design, ·RCS Chemistry, Deposition Expert team: Fuel Reliability, LOCA/non-LOCA, Radiological, RIA (External)
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FMEA and Design Review - Key Findings (1/9)
Source Potential Failure Mode Potential Cause/
framatome
Mechanism of Failure
Current Design Follow-up Action Controls
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Coating Technique to Improve Adherence
Ref: http://www.semicore.com/news/
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Coating Microstructure and Cr/Zr Interface
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Testing - Coating Adherence
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FMEA and Design Review_ - Key Findings (2/9) .
Potential Failure Mode
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Follow-Up Action
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FMEA and Design Review - Key· Findings (3/9)
Potential Failure Mode
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FMEA and Design Review - Key Findings (3/9)
Follow-up Action
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FMEA and Design Review - Key Findings (4/9)
Potential Failure Mode
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FMEA and Design Review - Key Findings ·(4/9)
Follow-up Action
I "-,, --
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FMEA and Design Review - Key Findings (5/9) . .
Potential Failure Mode Follow-up Action
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FMEA and Design Review - Key Findings (6/9)
Potential Failure Mode Follow-up Action
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FMEA and Design Review - Key Findings (7/9)
Potential Failure Mode Follow-up Action
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FMEA and Design Review - Key Findings (8/9)
Potential Failure Mode Follow-up Action
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FMEA and Design Review - Key Findings (9/9)
Potential Failure Mode Follow-up Action
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· FMEA and Design Review - Summary·
• Review boards identified the need for additional tes.t data to update/verify the applicability of c~rrent performance models
• Test Program has been revised and reprioritized based on recommendation from FMEA and Design Review Boards
• No new phenotj,enon or failure mode was ide.ntified for the Cr-coated cladding
• All recommendations shall be addressed in a timely manner and monitored to completion.
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. IN-PILE TESTING
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Cr-clad Irradiation Program ... -... ·. -.. - -&. - --~---·---~
ATR- 2018
ANO - 2019
Full-length L TRs
Full-length L TRs
framatome
Calvert Cliffs - 2021
Cr-Cr20 3 Full Assembly (LTAs)
I OSIRIS - 2015 )
Unfueled Cr-clad
Gosgen - 2016
& 2019
Cr-clad samples - (2016) Full Length LTRs (2019)
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Cr-Coated Clad. Irradiation Program
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[ ]
Cr-Coated Clad Irradiation Program
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[ ]
• ·OSIRIS and.Halden Irradiation
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[ ]
Cr-Coated Clad Irradiation Program
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[ . ]
Vis·ual Inspection of Cr-Coated Segments. _/
••• ••••• ••••••• ....... ...•... -Kernkraftwerk •:::• Gosgen
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IMAGO Irradiation - Schedule
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Cr-Coated Clad Irradiation Program
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[ . ]
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-ATR and TREAT - Irradiation and Testing
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ATR Irradiation - Schedule
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Cr-Coated Clad Irradiation Program
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[ ]
HFIR Irradiation Schedule
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Cr-Coated Clad Irradiation Program
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[ . ] .
Testing Program - Summary (1/3)
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Testing Program - Summary (2/3)
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Testing Program - Summary (3/3)
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Models.
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Models Summary (1/3)
Models Model changes Comments
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Models Summary (2/3) Models Model changes
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Models Summa:ry (3/3)
Models Model changes Comments
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Topical_ Report Outl_ine
I ss
Next Steps
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Acronyms
• ATF -Accident Tolerant Fuel • LTA- Lead Test Assembly • ATR -Advanced Test Reactor • L TR - Lead Test Rod
• BU - Burnup • NRC -. U._S. Nuclear Regulatory Comm1ss1on .
• BWR - Boiling Water Reactor • PCI - Pellet Cladding Interaction • CE - Conibustion Engineering • PIE - Post Irradiation Examination
• CEA - The French Alternative Energies and • PQD - Post Quench Ductility Atomic Energy Commission • PVD - Physical Vapor Deposition
• EATF - Enhanced Accident Tolerant Fuel • PWR - pressurized Water Reactor
• EOL - End of Life .. RAI - Request for Additional Information
• FMEA - Failure Modes and Effects Analysis • RPN - Risk Priority Number
• HT - High Temperature • TBD - To Be Determined . ' W - Westinghouse ·
• LOCA - Loss of Coolant Accident
· framatome ........
1 s9 EATF Status- Chromium Coated Cladding, February 27, 2019
Trademarks
AREA, ARITA, GALILEO and MS are ,trademarks or registered trademarks of -- Framatome or its affiliates, in the USA or other countries.
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Any reproduction, alteration, transmission to any third party or publication in whole or in part of this document and/or its
cc;>ntent is prohibited unless Framatome has provided its prior· · and written consent.
This document and any information it contains shall not be used for any other purpose than the one for which they were
provided. Legal action may be taken against any infringer and/or any person breaching the aforementioned obligations
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