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Higher Burnup Workshop Public Meeting - Accident Tolerant Fuel; June 10, 2021
	ML21159A140
Person / Time
Site:	Nuclear Energy Institute
Issue date:	06/10/2021
From:	; Nuclear Energy Institute
To:	; Office of Nuclear Reactor Regulation
	Orenak M
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	Download: ML21159A140 (32)
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Industry ATF Adoption Plans BEN HOLTZMAN, NEI

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2018 2019 2020 2021 2022 2023 2024 2025 2026 2027 SNC Hatch:

(GE/GNF)

SNC Vogtle:

(Framatome)

Exelon Byron:

(Westinghouse)

Exelon Clinton:

(GE/GNF)

Entergy ANO-1:

(Framatome)

Exelon Calvert Cliffs:

(Framatome)

Xcel Monticello:

(Framatome)

Key U.S. ATF Fuel Milestones Coated Cladding IronClad Enhanced UO2 Fuel High Density Fuel High Burnup LUA

+ Loadings

+/-

Loadings & Removal

+

Exelon Limerick:

(GE/GNF)

CRAFT/ESCP ROB DAUM, EPRI HATICE AKKURT, EPRI BILL GASSMANN, EXELON DAN WACHS, INL

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Rob Daum Sr. Technical Executive, EPRI Public Meeting - Higher Burnup Workshop II U.S. Nuclear Regulatory Commission June 10, 2021 Collaborative Research on Advanced Fuel Technologies for LWRs (CRAFT)

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6 Understanding the Benefits and Risks of LWR Advanced Fuel Technologies Safety, performance, and economic analyses of LWR advanced fuel technologies across the entire fuel cycle

- Accident Tolerant Fuel (ATF)

- Higher Burnup

- Increased Enrichment Gap analyses leading to collaborative and timely research to inform technical and licensing bases

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7 CRAFT Mandate and Purpose Foster research cooperation, collaboration, and coordination for LWR advanced fuel technologies Emulate the EPRI-led Extended Storage Collaboration Program (ESCP) on dry storage issues EPRI-NRC/RES MOU Addendum on ATF

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8 CRAFT Framework Objectives

1. Bring together subject matter experts from U.S. organizations, and when appropriate international organizations, engaged with active or planned RD&D in the ATF, higher burnup, and/or higher enrichment fuel areas for LWRs.

2. Identify both short and long-term technical options and recommendations for supporting the industrys generic and highest priority RD&D needs for topical and licensing submittals and associated regulatory reviews.

1. Identify options and recommendations for addressing RD&D issues such as test/resource planning, data collection, and analysis; and determine potential areas for formal collaborations.

2. Communicate options and recommendations to stakeholders for decision-making activities.

3. Support gap analyses and/or Phenomenological Issues Ranking Table (PIRT) processes. Documentation of the gap analyses results are a key part of responsibilities of the collaboration.

4. Compile, analyze and synthesize generic RD&D results to form/inform technical bases in targeted deliverables to meet the needs and timelines for submittals and reviews associated with advanced LWR fuel licensing and deployment.

Industry DOE/

National Labs Regulatory Research Academia Intl NEA / IAEA EPRI

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9 CRAFT Technical Focus and Status CRAFT meetings started virtually in 2020 to review/adjust proposal and solicit stakeholder commitments to participate Defined a framework charter and issues on in-reactor generic issues associated with Fuel Fragmentation, Relocation, and Dispersal (FFRD)

Support higher burnup (~75 GWd/MTU peak rod average)

U.S.-focused but will engage international R&D community and stakeholders Technical Expert Groups reviewing specific technical issues related to FFRD to develop a coordinated research plan by 3rd quarter 2021 Experiments and modeling-simulation Analytical models Risk-informed approaches CRAFT Framework

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Hatice Akkurt Technical Executive Used Fuel and High-Level Waste Management Program High Burnup Workshop June 10, 2021 ESCP & Other Back-End Activities for Advanced LWR Fuels

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11 Extended Storage Collaboration Program (ESCP)

Mission

Enhance the technical bases to ensure continued safe, long term used fuel storage and future transportability Goals

Bring together US and International organizations engaged with active or planned R&D in used fuel area

Share information

Identify common goals and needs

Identify potential areas of formal collaborations Phases

Phase 1: Review current technical bases and conduct gap analysis for storage systems

Phase 2: Conduct experiments, field studies, and additional analyses to address gaps

Phase 3: Long-term performance confirmation

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12 ESCP History 2009 1st ESCP meeting 1 country, 39 participants 2 subcommittees 2010-2019 Regular May and December meetings, in US 14 International meetings 6 subcommittees 2021

~675 members from 22 countries Over 315 participants, representing 12 countries, attended Winter 2020 meeting 4 subcommittees

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13 ESCP Structure - Subcommittees (SCs) and Task Groups (TG) - After 2021 Steering Committee Meeting ESCP Steering Committee Chair: Hatice Akkurt (EPRI)

Fuel Assembly Chair: Mike Billone (ANL)

Advanced Fuels (ATF, HBU, HE)

Sven Bader (Orano)

Modeling & Benchmarking Chair: Maik Stuke (BGZ)

Thermal Lead: David Richmond (PNNL)

Decay Heat Lead: Fredrik Johansson (SKB)

Radiation Dose Lead: Kaushik Banerjee (PNNL)

Canister Integrity/Aging Management Chair: Bob Hall (EPRI)

Aging Mechanisms and Consequence Leads: Sam Durbin (SNL) and Jimmy Burns (UVA)

Mitigation and Repair Leads: Greg Frederick (EPRI) and Allen Williams (SONGS)

Monitoring/Sensors Lead: Al Csontos (EPRI)

University Collaboration Lead: Jon Tatman (EPRI)

International Subcommittee Co-chairs: David Hambley (NNL),

Woo-seok Choi (KAERI), Brady Hanson (PNNL)

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14 Activities for Back-end for Advanced LWR Fuel (HBU/HE/ATF)

EPRI CRAFT General Guidance and Analyses Technical Experts Group (GGATEG)

NRC Higher Burnup Workshop II June 10, 2021 Bill Gassmann Exelon Nuclear

GGATEG Charter Inform industry, DOE, and NRC of the pressing technical issues regarding deployment of higher burnup and higher enrichment LWR fuel Focus on generic research needs to inform issues, including Alternate licensing approaches Safety analyses Core physics and neutronics Members include US DOE/National Labs Fuel vendors NRC Utilities NEI EPRI 16

GGATEG Scope Research and assessments of generic guidance and alternate approaches for understanding and informing the technical bases for use in industrys fuel licensing submittals and regulators reviews

FFRD

Fuel rod burst analyses and consequences under DBAs

Higher burnup/enrichment core design analyses Investigate existing and new methods and analytical tools for deterministic, best estimate and risk-informed approaches Major areas of investigation

Fuel relocation

Fuel dispersal

LBLOCA/xLPR/LBB

SBLOCA/IBLOCA

Cladding rupture analyses

Higher burnup/enrichment fuel management

PSA modeling

Safety margin evaluation

Defense in depth analyses 17

Update on Fuel Performance and Testing Technical Experts Group Dr. Daniel Wachs National Technical Director, Advanced Fuels Campaign Idaho National Laboratory 18 NRC High Burnup Meeting Web meeting, June 10, 2021

Complementary Roles in U.S. Nuclear Technology Enterprise

Collaboration on Research and Development for Fuel Technology (CRAFT)

Fuel Performance and Testing Technical Experts Group (FPT TEG)

General Guidance and Analysis Technical Experts Group (GGA TEG)

TEG Overview

Both TEGs are tasked with coordinating technical input and data that can be used to inform industrial users, regulators, and researchers

TEGs are populated with cross-cutting stakeholder representatives (utilities, fuel vendors, national lab, NRC, EPRI, )

FPT TEG doesnt fund, conduct, or direct independent R&D

Information is developed through regular meetings and workshops and transmitted to the CRAFT governing board

Strategy for Next Generation LWR Fuel Technology

Understanding the relationship between ATF and HBu is important to various stakeholders

Burnup Extension

Phase 1 - Deployment of current fuel designs to 65-68 GWD/MTU

Little to no new data required to support licensing

Several topicals already submitted

Phase 2 - Deployment of current fuel designs to >75 GWD/MTU

Must have sufficient data to resolve HBU fuel performance questions (most notably FFRD)

Anticipated by mid-2020s

ATF

Deployment of near-term technologies

Batch reloads to current regulatory limits by mid 2020s

Integrated ATF/HBU

Deployment of ATF to high burnup w/ optimized utilization margins by ~2030 20

Current LOCA R&D Needs

High burnup fuels (> ~68 GWd/t)

Thresholds and extent of fuel fragmentation

Thresholds and impacts of fuel relocation

Thresholds and impacts of fuel dispersal

Reduced uncertainty in transient fission gas release

Effect of fully prototypic LOCA conditions temperature evolution (blowdown from full power)

No tests to date but differences manifest between in-pile and hot cell LOCA tests

Integral In-Pile LOCA Testing considered most important R&D need for HBU fuels

However, additional data needs will naturally be met under this umbrella

Expanded HBu fuel performance database (code validation)

Confirmatory LOCA Furnace Testing

Data for assessment of transient fission gas behavior

Validation of RIA performance at HBu FFRD HBU Integral LOCA database (Halden) - 7 PWR, 4 BWR, 2 VVER 72 GWd/MTU from Studsvik furnace test Note: High Burnup BWR data needs are driven by operational behavior rather than licensing

Draft CRAFT HBu Roadmap 22

Roadmap for FFRD Assessments 23 High Priorities 2020 2021 2022 2023 2024 2025 2026 Technical and Licensing Bases for Fuel Fragmentation, Relocation, and Dispersal for Higher Burnup (<75 GWd/MTU)

Operations Alt. Licensing Approaches - Phase 2 Alt.

Licensing Approach No Fuel Rod Burst LOCA Approaches LTR Submission Pre-Submittal Mtgs with NRC Approval Integral/Separate Effects Testing and Modeling of non-ATF Higher Burnup Fuel Fine Fuel Fragment Dispersal Consequence Analyses Technical BasisReport Utility LAR Submission Fuel Rod Burst LOCA/RIA Approaches Vendor LTR Submission Collaborative Research on Advanced Fuel Technologies (CRAFT) Framework / Technical Workshops NRC Review NRC Review Approval Higher Burnup ATF Testing

TREAT LOCA Experiment Plan AFC LOCA experiments on irradiated fuels, LOC-HBU NSUF ATR reirradiation of commercial HBU fuel LOC-C, LOCA Commissioning 2021 2022 2023 2024 2025 Phase I Phase II ATF/HBU FOA LOCA Support (expected Flowing Loop Commissioning LOC-C: LOCA Commissioning (Fresh Fuel)

2 power calibration tests

1 thermal hydraulic characterization test (~5 transients)

2 thermomechanical control tests/ATF LOC-HBU: High Burnup LOCA Experiments for FFRD*

GWd/t

1 Halden tieback experiment (IFA 650.10, 650.15) 65

1 Prototypic thermal evolution comparison 65

2 Very HBU power history effects tests 75

1 Very HBU doped fuel 75

2 BU limit/beyond 85 Preliminary LOCA Experiment Matrix Working with ORNL for complementary hot cell LOCA tests, recent HBU LOCA furnace results shown above, courtesy Jason Harp, ORNL Out-of-Pile LOCA Prototype and Instrument Qual in HTTL NEA/AFC/IRSN LOCA Program (planned)

INL Byron Fuel Shipment INL <-> ORNL Studsvik ORNL Byron Fuel Shipment

Modeling for Experiment Design RELAP5-3D RELAP5-3D

TREAT LOCA Strategy

Designed to provide representative fuel &

cladding temperature control 100% nuclear heating in specimen Peak temperatures ~ > cladding melting Heating rate > 2 °C/s Blowdown valve Capsule holds 6-24 fuel specimen Expansion Tank TWIST Capsule Outer Containment TREAT LOCA sequence Pre-Transient Ops Transient Segment 1 Transient Segment 2 SCRAM

(& reflood possible)

-10 hrs t = -10 sec t = 0 sec

~2-4 min Initiate Transient Reactor Power Fuel Temp.

Cladding Temp.

Initiate Blowdown &

Power Decrease Full Power, thermal conditioning Low Power, fission product activation Decay heating to desired level

Unique real-time diagnostics Fuel motion monitoring system Cladding balloon extent Non-contact balloon temperature measurement Fuel centerline temperature Rod plenum pressure (fission gas release)

Cladding thermocouples Hodoscope commissioning in SETH experiments

Summary

Fuel Performance and Testing TEG is populated with technical leaders from all stakeholders

Critical path technical questions have been identified and R&D projects to assess them are formulated

LOCA testing capabilities are in being implemented (in-pile and out-of-pile)

HBu source materials have been identified and are being sent to the two national labs 27

Risk-Informed Method for FRRD NIMA ASHKEBOUSSI, NEI

AST vs Normal Source Term BEN HOLTZMAN, NEI

©2021 Nuclear Energy Institute 30 Normal vs Alternate Source Term Method Alignment between Reg. Guide 1.183 efforts and industry plans Ensure no artificial restrictive limits Will updated source term calculations be required for ATF implementation?

ATF Source Term Discussion

Severe Accident PIRT Impacts BEN HOLTZMAN, NEI

PIRT applied lessons learned from previous coated cladding PIRT for improved process and transparency Future engagement on MELCOR and MAAP alignment PIRT Highlights

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