proposed 2017-2018 project portfolio · proposed 2017-2018 portfolio discussion of key u nfunded...

© 2016 Electric Power Research Institute, Inc. All rights reserved.

Rick ReidProgram Manager

Used Fuel and High Level Waste Technical Advisory Committee Meeting

Tuesday, August 30, 2016

Proposed 2017-2018 Project Portfolio

Date: 04 August 2016, Rev. 0

2© 2016 Electric Power Research Institute, Inc. All rights reserved.

Used Fuel and HLW Management Program Technical Advisory Committee Meeting Meeting Holder: Rick Reid, ([email protected])

Room Location: Roosevelt BR – Salon 2 (ML)


Time Topic Lead

8:00 am Welcome and Introductions Z. Martin, TVA R. Reid, EPRI

8:05 am

Overview of 2017-2018 Projects Prioritization Results Proposed 2017-2018 Portfolio Discussion of Key Unfunded Projects Endorsement of 2017-2018 Portfolio

R. Reid, EPRI All

9:45 am Five-Year Plan R. Reid, EPRI

10:00 am Break All

10:30 am Utility Experience Sharing

12:00 pm Lunch - Crescent City Ballroom (Mezzanine Level) All

1:00 pm Utility Experience Sharing (Continued)

2:00 pm Round Table: Strategic Planning All

3:00 pm Break All

3:30 pm Meeting Summary TAC Action Items for APC Meeting Plus/Deltas

All

4:00 pm Adjourn All (except as noted below)

4:10 pm Presentation Material for APC Z. Martin, TVA S. LeBlang, Entergy EPRI Staff

5:00 pm Adjourn Remainder

Used Fuel and HLW Management Program Technical Advisory Committee Meeting

Meeting Holder: Rick Reid, ([email protected])

Room Location: Roosevelt BR – Salon 2 (ML)


Time

Topic

Lead

8:00 am

Welcome and Introductions

Z. Martin, TVA

R. Reid, EPRI

8:05 am

Overview of 2017-2018 Projects

· Prioritization Results

· Proposed 2017-2018 Portfolio

· Discussion of Key Unfunded Projects

· Endorsement of 2017-2018 Portfolio

R. Reid, EPRI

All

9:45 am

Five-Year Plan

R. Reid, EPRI

10:00 am

Break

All

10:30 am

Utility Experience Sharing

12:00 pm

Lunch - Crescent City Ballroom (Mezzanine Level)

All

1:00 pm

Utility Experience Sharing (Continued)

2:00 pm

Round Table: Strategic Planning

All

3:00 pm

Break

All

3:30 pm

Meeting Summary

· TAC Action Items for APC

· Meeting Plus/Deltas

All

4:00 pm

Adjourn

All (except as noted below)

4:10 pm

Presentation Material for APC

Z. Martin, TVA

S. LeBlang, Entergy

EPRI Staff

5:00 pm

Adjourn

Remainder


Prioritization Results Summary

24 of 32 utilities responded (75%)– 18 of 23 US utilities (78%)– 6 of 9 non-US utilities (67%)– All “fleet” utilities responded

Research Focus Area High Medium Low AverageAging Management of Dry Fuel Storage System Components 15 8 1 1.4

Used Fuel Cladding Performance during Extended Storage and Transportation 10 14 0 1.6

Criticality Control during Used Fuel Storage and Transportation 7 10 7 2.0

Technical Basis for Disposition of Used Nuclear Fuel 0 8 16 2.7


Prioritization Results (percentage of respondents)

Aging Management of Dry Fuel

StorageComponents

Average 1.4 (High)

Used Fuel Cladding Performance

during Extended Storage and

Transportation

Average 1.6 (Medium)

Criticality Control during Storage

and Transportation

Average 2.0 (Medium)

Technical Basis for Disposition of

Used Nuclear Fuel

Average 2.7 (Low)

63

334

42

58

29

42

29 33

67

High Medium Low


Aging Management of Dry Fuel Storage System Components

Project types Typical deliverables Specific near-term activities

• Guidance development • Guidance documents• Training workshops • Stainless steel canister aging management guidance

• Technical basis development • Technical reports • Consequence analysis for CISCC in stainless steel canisters

• Inspection method development • Technical reports• Demonstrations

• Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems

Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel

canisters Other issues could include degradation of seals in bolted metal cask designs or

degradation of concrete over packs in canister-based systems. Work includes failure modes evaluation, development of aging management guidance,

development of inspection techniques, development of mitigation and repair techniques, etc.



Aging Management

of DSCC

Canister Aging Management

(2017-2021)

Advanced NDE (2017-2021)

Repair and Mitigation

(2017-2020)

Consequence Analysis

(2017-2018)

High Priority

Mean = 1.40

Median = 1

Sample Feedback: The Consequence Analysis work and the SS canister aging

management work are of highest priority for the industry to be able to influence NRC's Risk Informed approach to aging management of dry cask systems.

Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks. Work on cask seals would be high priority.

Stainless steel canister NDE and delivery systems should have the highest priority within this RFA.

I would like to see some work on leak rates through thru-wall cracks under prototypical cask conditions. Also, work on repair techniques for cracks, if discovered, would also be helpful.

Portfolio Recommendations:

Fund continuing projects

Fund consequence analysis

Delay work on repair and mitigation pending efforts by the ESCP subcommittee, and vendors

Funded Unfunded

63

334

High Medium Low


Used Fuel Integrity during Extended Storage and Transportation

Project types Typical deliverables Specific near-term activities• Testing and evaluation of used

fuel during storage • Technical reports• High burnup fuel confirmatory data project

• Fundamental R&D on the effect of irradiation on fuel cladding materials

• Technical reports• Collaborative test programs to determine the effect

of irradiation on cladding performance in high burnup fuel

Current focus is understanding material properties of cladding materials in high burnup fuel– Properties may change during storage– Critical to determination of performance under normal and accident loads that may

occur during transportation– The potential for hydride reorientation is a principal concern

Generation of data to predict the performance of differing cladding types is a key element in the research focus area– Data on advanced cladding materials ideally available prior to transfer to dry storage,

but must be available prior to transport



Used Fuel Integrity

High Burnup Data Project

(2017+)

Cladding Performance

(2017+) Medium Priority

Mean = 1.6

Sample Feedback: The high burnup project is currently the industry's highest

priority. Project High Burnup Demo is high priority. High Burnup Issues

Resolution is of medium priority Additional tests will be interesting to know the ZIRLO behavior

after hydride reorientation when the maximum temperature achieved during drying is lower than 400ºC (for example, 350ºC)

The use of a modified loaded MPC canister, with various fuel types, and analysis of the high burn-up fuel rods to determine effects, will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel Due to the EPRI/DOE agreement, this should be funded.


Fund both continuing projects

Funded Work Unfunded

High Medium Low

42

58


Criticality Control during Used Fuel Storage Work in this research focus area includes

– Evaluation of long-term performance of neutron absorbing materials– Improvement of computational models used to determine criticality safety margins– Experimentally derived benchmarks for assessing the bias and uncertainty of

computational model– Development of in-situ and ex-situ test methods for evaluating the performance of

neutron absorbing materials


• Material testing • Technical reports• Zion comparative analysis project• Accelerated corrosion testing of Boral specimens

• Guidance and benchmarking • Technical reports

• PWR and BWR reactivity depletion benchmarks

• Users group • Meetings and webcasts • Neutron Absorbers Users Group


Criticality Control during Used Fuel Storage

Criticality Control during

Used Fuel Storage

PWR Reactivity Depletion

(2011-2017)

BWR Reactivity Depletion

(2017-2019)

Neutron Absorber Handbook

(2017-2018)

Neutron Absorber

Degradation(2017+)

Medium Priority

Mean = 2.0

Sample Feedback: With the increased focus by the NRC on neutron absorber aging,

the Neutron Absorber Degradation work will allow industry to provide justification for any proposed monitoring programs. In addition, the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained.

Medium priority for the project "Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation". Low priority for the other projects.

For plants with no Boral coupons installed in their SFP (or dry canisters), it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data, Zion test data, etc.


Fund all continuing projects

Delay revision of the Neutron Absorber Handbook to 2019 or 2020


High Medium Low

29

42

29


Technical Basis for Disposal of Used Nuclear Fuel


• Technical evaluations • Technical reports• No near-term activities

No current work Future work might include technical basis for disposal and/or long-term management

plans being considered in member countries:– Assistance with performance and risk assessments– Input to environmental impact assessments– Technical input to risk assessments associated with transportation of fuel for long-

term storage at centralized interim storage facilities.



Technical Basis for

Disposal of Used Nuclear

Fuel

Low Priority

Mean = 2.70

Sample Feedback: Medium priority for the project "Technical input to risk

assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities". Low priority for the rest of the work.

Near term focus should be on transportation and long-term storage at CIS facilities.

While this will eventually become important, it is not a critical issue of today and there is time to deal with this.

Cost is relatively low to continue an international dialogue and help leverage outside funding to EPRI desired contracts.


N/A


High Medium Low

33

67


Proposed 2017-2018 Portfolio

Project Name Year2017 2018

RFA: Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management 350 350SS canister: Advanced NDE and Delivery systems 500 500Canister Consequence Analysis 400 125SS canister: Repair and mitigation techniques/options 0 0

RFA Total 1250 975RFA: Used Fuel Cladding Performance during Extended Storage and

TransportationHigh Burnup Data Project 1287 1462High Burnup Issues Resolution – Cladding Performance 400 400

RFA Total 1687 1862RFA: Criticality Control during Used Fuel Storage and Transportation

PWR Reactivity Depletion - "EPRI Methodology" 150 0BWR Reactivity Depletion - "EPRI Methodology" 100 450Neutron Absorber Material Degradation 730 630Neutron Absorber Handbook 0 0

RFA Total 980 1080Unassociated Projects

Extended Storage Collaboration Program 250 250

CFD of Partial SFP Draindown Scenario 0 0Total Of Funded Projects 4167 4167

Fund All Continuing

Projects

3 New Projects Not

FundedRed – Not Funded

Black - Funded


Unfunded Projects

Canister Repair and Mitigation– Manage through ESCP subcommittee– Work with NEI and vendors to develop a work planNeutron Absorber Handbook Revision

– Defer to 2019 or 2020Spent Fuel Pool Computational Fluid Dynamics Study

– Verify need for the effort and seek alternative funding, if warranted


Together…Shaping the Future of Electricity


Project Summaries




• Guidance development • Guidance documents• Training workshops • Stainless steel canister aging management guidance

• Technical basis development • Technical reports • Consequence analysis for CISCC in stainless steel canisters

• Inspection method development • Technical reports• Demonstrations

• Development and demonstration of NDE techniques and delivery systems for inspection of dry cask storage systems

Would address all areas associated with dry storage systems Current focus is on chloride-induced stress corrosion cracking in stainless steel

canisters Other issues could include degradation of seals in bolted metal cask designs or

degradation of concrete over packs in canister-based systems. Work includes failure modes evaluation, development of aging management guidance,

development of inspection techniques, development of mitigation and repair techniques, etc.


Welded Stainless Steel Canister Aging Management

Issue– Chloride-Induced Stress Corrosion Cracking (CISCC) is a

potential degradation mechanism for used fuel storage canisters in dry cask storage systems; license renewal activities have been impacted with requirements to address this issue in learning aging management programs

Key activities– Provide implementation training for aging management

guidance – Support ASME Task Group on In‐service Inspection of Spent

Fuel Storage and Transportation Containments

Value– Provide guidance on actions necessary to support risk-

informed aging management of stainless steel canisters


Stainless Steel Canister Non-Destructive Examination Techniques and Delivery Systems Issue

– Due to potential for degradation, inspection of storage canisters may be required

– Canister designs not immediately amenable to inspection using established NDE techniques and delivery systems

Key activities– Continue development and mock-up testing of promising

NDE techniques– Continue development of delivery systems– Continue system refinement and demonstration on empty

canisters – Conduct demonstration on a loaded canister

Value– Develop new technology needed to conduct required

inspections


Through-wall CISCC Consequence AnalysisNew Project (Follow up to 2016 effort) Issue

– Regulators are beginning to develop risk-informed regulatory approach to used fuel storage and transportation

– Actual consequences of a through-wall CISCC flaw are expected to be very low but have not been fully analyzed and documented

– Demonstration of low consequences could provide justification for reduced/eliminated inspections during extended storage

Key activities– Utilize results and recommendations from 2016 scoping study to develop one or more

generically applicable analyses to show consequence of unmitigated through-wall CISCC for a storage period of 60-100 years

– Interact with NRC/ACRS/NEI and other stakeholders to build a case for using site boundary dose as a surrogate for Large Early Release Frequency in a Risk-Informed approach

Value– Develop technical basis for risk-informed canister aging management


Mitigation/Repair of Welded Stainless Steel CanistersNew Project – Not Funded Issue

– Inspections of welded canisters will begin taking place in 2017 to fulfill ISFSI license renewal commitments

– Industry is lacking qualified techniques for mitigation and repair following any “unacceptable” inspection finding

Key activities– Evaluate techniques that have been applied for mitigation and repair of

operating components that are susceptible to PWSCC for application to welded canisters.

– Investigate technologies that may be uniquely applicable to canisters– Provide recommendations for further efforts to develop and demonstrate viable

techniques Value

– Provides a starting point for development of canister-specific repair and mitigation techniques, leveraging previous work on reactor components



Project types Typical deliverables Specific near-term activities• Testing and evaluation of used

fuel during storage • Technical reports• High burnup fuel confirmatory data project

• Fundamental R&D on the effect of irradiation on fuel cladding materials

• Technical reports• Collaborative test programs to determine the effect

of irradiation on cladding performance in high burnup fuel

Current focus is understanding material properties of cladding materials in high burnup fuel– Properties may change during storage– Critical to determination of performance under normal and accident loads that may

occur during transportation– The potential for hydride reorientation is a principal concern

Generation of data to predict the performance of differing cladding types is a key element in the research focus area– Data on advanced cladding materials ideally available prior to transfer to dry storage,

but must be available prior to transport


High Burnup Spent Fuel Data Project(aka the HBU Demo) Issue

– Lack of data on high burnup fuel under dry storage conditions– Conduct a full scale, long term research project to determine the effect of dry storage

on high burnup cladding under typical conditions Key Activities

– Complete fabrication of the cask and instrumentation– Load the cask– Collect data (temperatures, gas composition)

Value– Provides confirmatory data to show that high burnup fuel may be safely stored and

transported– Supports industry license renewal commitments (US)


High Burnup Issues Resolution – Cladding Performance

Issue– Data on “advanced” claddings (ZirloTM, Optimized ZirloTM, M5, AXIOM, etc.) are

needed to verify that the performance of these claddings will meet the regulatory requirements applicable to dry storage and transportation conditions

Key Activities– Examinations of high-burnup fuel in hot cells through active collaborations with: EDF R&D Nuclear Fuel Industry Research (NFIR) Group

Value– Leverages global R&D on high burnup cladding properties– Forms continuing technical basis for the safe storage and transportation of high

burnup fuel using advanced cladding materials– Provides early identification of any cladding-type specific issues


Criticality Control during Used Fuel Storage Work in this research focus area includes

– Evaluation of long-term performance of neutron absorbing materials– Improvement of computational models used to determine criticality safety margins– Experimentally derived benchmarks for assessing the bias and uncertainty of

computational model– Development of in-situ and ex-situ test methods for evaluating the performance of

neutron absorbing materials


• Material testing • Technical reports• Zion comparative analysis project• Accelerated corrosion testing of Boral specimens

• Guidance and benchmarking • Technical reports

• PWR and BWR reactivity depletion benchmarks

• Users group • Meetings and webcasts • Neutron Absorbers Users Group


Spent Fuel Pool Criticality: Depletion Benchmarks for Full Burnup Credit Validation Issue and Background

– 2010 regulatory guidance reduced reactivity decrement due to fuel burnup– EPRI methodology and benchmarks, and associated NEI Criticality Guidance (NEI 12-16)

under review by US NRC Key Activities

– Continue to respond to and resolve issues identified in the RAIs from the NRC on the EPRI PWR Benchmarks and NEI documents

– For BWR benchmarks, conclude the feasibility study and publish a report that describes the path forward Discuss the feasibility study results with stake holders, including utilities and regulators Perform the development of benchmarks, pending on feedback

Value– Provides technical basis and approach for reduced uncertainty in the reactivity decrement,

ultimately preserving SFP criticality margins and loading capability


Neutron Absorber Material Degradation Issue

– Current materials may be prone to degradation; R&D needed to identify and characterize degradation modes, quantify the effect of degradation on material performance, and develop monitoring and aging management programs.

Key activities (Ongoing projects)– Accelerated corrosion test: remove and evaluate fourth-year coupons; compare to

results from previous years– Zion project: complete analysis of coupons, in-situ measurements and specimens

from harvested panels and publish the final report that compares results from these three measurements

– Neutron Absorbers Users Group: conduct annual meeting (July 2017) Key activities (New project)

– Development of alternative neutron absorber material monitoring approach Value

– Provides the technical basis for aging management of neutron absorber materials


Neutron Absorber MaterialsNew Project: Update of Neutron Absorber Material Handbook – Not FundedNeutron Absorber Handbook published in 2009

– Since then, there have been many changes in material development, operational experience, regulatory perspectives

Objective: Update Neutron Absorber Material Handbook Scope and Approach: Review the handbook and

Revise the content, as needed Include new developments in

– Neutron absorber materials, – Operational experience,– Regulatory perspectives

Anticipated Deliverable: Publication of new version of Neutron Absorber Material Handbook as EPRI report in 2018Value

– Provides an up-to-date resource on neutron absorber materials




• Technical evaluations • Technical reports• No near-term activities

No current work Future work might include technical basis for disposal and/or long-term management

plans being considered in member countries:– Assistance with performance and risk assessments– Input to environmental impact assessments– Technical input to risk assessments associated with transportation of fuel for long-

term storage at centralized interim storage facilities.


Projects not Associated to a RFA


Extended Storage Collaboration Program (ESCP)

Key Activities and Anticipated Deliverables– One day ESCP meeting in May and 3-day meeting in DecemberWhen possible, conduct International subcommittee meeting Periodic subcommittee meetings via webcast or teleconference

– Publication of International Data Gap report– Work on NDE Subcommittee report– Participation in global industry group meetingsValue

– Allows leveraging of global work being performed in the used fuel management area

– Provides a forum to prioritize and coordinate R&D globally


CFD Study of Partial SFP Drain DownNew Project – Not Funded Issue

– A partial drain down scenario may be the most limiting with respect to the potential for a “zirconium fire.” This scenario has not been fully evaluated. Due to the lack of this evaluation, plants in a decommissioning status must maintain full emergency response capability for 18 months after plant shutdown until the risk of zirconium fire is greatly reduced.

Key Activities– A computational fluid dynamics study of the partial spent fuel pool drain down

scenario will be performed to determine the conditions under which a zirconium fire could occur.

– This study will include a number of drain down levels, and for each level, will determine the time fuel temperature would approach that required for zirconium auto-ignition (about 1000°C /1832°F) as a function of fuel cooling time.

Value– Potential reduction in the time after shutdown that full emergency response must be

maintained


All Prioritization Comments


Aging Management of Dry Fuel Storage System ComponentsComments Issues with corrosion due to sea proximity The Consequence Analysis work and the SS canister aging management work are of highest

priority for the industry to be able to influence NRC's Risk Informed approach to aging management of dry cask systems.

Priority for projects with SS Canister Storage Technology is low priority since utility uses bolted casks. Work on cask seals would be high priority.

Davis-Besse will be the first General Licensee on the hook to execute the ISFSI aging management program.

Risk informed storage/consequence analysis need to maintain priority. Stainless steel canister NDE and delivery systems should have the highest priority within this

RFA. I would like to see some work on leak rates through thru-wall cracks under prototypical cask

conditions. Also, work on repair techniques for cracks, if discovered, would also be helpful. Though this project is critical to avoid unwanted regulation at all used fuel storage sites, it is likely

the lowest priority RFA based on the notes regarding priority, as listed below for the other RFAs. This would be the RFA to demote to a "3" if it is not okay to have three RFAs prioritized as "2".

The consequence analysis should be among the highest priority items in this RFA. Demonstrating that the consequences of a cask breach are minimal will help in justifying lower inspection frequencies and intensities for dry storage during renewals.


Used Fuel Cladding Performance during Extended Storage and TransportationComments

The high burnup project is currently the industry's highest priority. Project High Burnup Demo is high priority. Our level of burnup is 60

GWD/MTU approximately. High Burnup Issues Resolution is of medium priority Collect and classify existing tests with different materials (ZIRLO, ZRY2,

M5,...) and conditions (max. temperature, cooling rate, H2 contents,...) for gap identification and general conclusions. * Additional tests will be interesting to know the ZIRLO behaviour after hydride reorientation when the maximum temperature achieved during drying is lower than 400ºC (for example, 350ºC) and the Ductile-Brittle Temperature Transition in this case. The use of a modified loaded MPC canister, with various fuel types, and

analysis of the high burn-up fuel rods to determine effects, will provide all HBU sites with additional knowledge regarding long term storage and shipment of fuel. Due to the EPRI/DOE agreement, this should be funded.


Criticality Control during Used Fuel Storage and TransportationComments With the increased focus by the NRC on neutron absorber aging, the Neutron Absorber

Degradation work will allow industry to provide justification for any proposed monitoring programs. In addition, the Criticality Analysis Depletion methods are priority to ensure industry margins are maintained.

We are watching old/new/alternative neutron absorbing materials for both purposes (SF pools + metal casks).

for spent fuel pool / boral research - ensure we are adequately supporting the NEI initiative on boral corrosion and SFP chemistry guidelines. Also, ensure we are supporting technical basis on current criticality calculation methodology concerns from the NRC.

Medium priority for the project "Development and Regulatory Acceptance of BWR Depletion Benchmarks for Full Burnup Credit Validation". Low priority for the other projects.

Depending on the outcome of the NRC GL2016-01 submittals, the Neutron Absorbing Materials project could have the highest priority within this RFA.

For plants with no Boral coupons installed in their SFP (or dry canisters), it is imperative that EPRI develop data to support anticipated neutron absorber degradation through use of industry wide available test data, Zion test data, etc.


Technical Basis for Disposition of Used Nuclear FuelCommentsNo projects listed. N/A. Medium priority for the project "Technical input to risk

assessment associated with transportation of fuel for permanent disposal or long-term storage at centralized interim storage facilities". Low priority for the rest of the work. Near term focus should be on transportation and long-term

storage at CIS facilities. While this will eventually become important, it is not a critical

issue of today and there is time to deal with this. Cost is relatively low to continue an international dialogue

and help leverage outside funding to EPRI desired contracts.

© 2016 Electric Power Research Institute, Inc. All rights reserved.

Rick ReidProgram Manager

Used Fuel and High Level Waste Technical Advisory Committee Meeting


Five-Year Plan2017-2021

Date: 04 August 2016, Rev. 0


Five-Year Plan: 2017-2021Project Name 2017 2018 2019 2020 2021

RFA: Aging Management of Dry Fuel Storage System ComponentsStainless Steel Canister Aging Management SS canister: Advanced NDE and Delivery systems Canister Consequence Analysis SS canister: prevention and mitigation techniques/options

RFA: Used Fuel Cladding Performance during Extended Storage and TransportationHigh Burnup Demonstration Project High Burnup Issues Resolution – Cladding Performance

RFA: Criticality Control during Used Fuel Storage and TransportationPWR Reactivity Depletion - "EPRI Methodology" BWR Reactivity Depletion - "EPRI Methodology" Neutron Absorber Material Degradation Neutron Absorber Handbook

Unassigned ProjectsExtended Storage Collaboration Program New Projects 778K 1057K 2.4M


Extended Storage Goals and Trajectory (1/2)

Technical bases for – Long-term storage aging management plans– Transportation after long-term storage On-going activities:

– 2017: Finalize stainless steel canister aging management guidance; follow ASME code case development

– 2017-2018: Complete consequence analysis– 2017-2021: Complete development and deploy NDE techniques– 2013-2019: High burn up demonstration– Continuing: High burnup fuel - cladding performance

Fundamental data on the behavior of dry storage systems and fuel over multiple decades to support sensible aging management.


Extended Storage Goals and Trajectory (2/2)

Potential near-term activities (2017 – 2021):– concrete over pack aging management guidance– stainless steel canister degradation mitigation and repair options,

and design and loading considerations– high burn-up demonstration: support for transport licensing Longer-term activities:

– continue Extended Storage Collaboration Program– high burn-up demonstration: long-term data collection followed by

cask reopening


Criticality Goals and Trajectory Technical bases for

– PWR spent fuel pool criticality calculation – Neutron absorber material aging management– BWR spent fuel pool criticality calculation

Current and near-term activities– 2013-2018: Boral coupon accelerated corrosion testing– 2015-2016: NRC acceptance of PWR SFP criticality methodology– 2015-2017: Zion coupon measurements and panel harvesting– 2016-2019: BWR SFP criticality methodology– 2017-2019: Enhanced monitoring techniques– 2020: Neutron Absorber Handbook revision

Longer-term and continuing activities: Neutron Absorber Users Group

Maintain Maximum Spent Fuel Pool Storage Flexibility


Other Potential Near-Term Projects/Project Areas (1/2)

Geological disposal: evaluation of technical issues associated with deep geological disposal of used fuelCentralized interim storage: experience summary and evaluation of

technical issues associated with interim storage of used fuel in centralized (non-power plant) facilitiesDry Storage Handbook revision: last updated in 2011Hydride Reorientation: report providing a summary of research

efforts to close out this issueAging Management of Bolted Cask Seals: initial analysis to

determine technical issues ISFSI Security: review technical basis work being developed by US

DOE


Other Potential Near-Term Projects/Project Areas (2/2)

License Renewal Guidance: focus on implementation activitiesTransportation of Used Fuel: technical basis for transportabilityAging Management of Metamic and Borated Stainless Steel:

evaluation of potential degradation modes and effect on performanceNeutron absorber coupon database: repository of industry

data on the results of coupon analysesSpent Fuel Pool water chemistry control: technical basis for

water chemistry optimization to mitigate absorber degradationSpent Fuel Pool accident analyses: technical analysis of

credible postulated spent fuel pool accidents


Together…Shaping the Future of Electricity

Proposed 2017-2018 Project PortfolioSlide Number 2Prioritization Results SummaryPrioritization Results (percentage of respondents)Aging Management of Dry Fuel Storage System ComponentsAging Management of Dry Fuel Storage System Components�Used Fuel Integrity during Extended Storage and TransportationUsed Fuel Integrity during Extended Storage and Transportation�Criticality Control during Used Fuel StorageCriticality Control during Used Fuel Storage�Technical Basis for Disposal of Used Nuclear FuelTechnical Basis for Disposal of Used Nuclear Fuel�Proposed 2017-2018 Portfolio�Unfunded ProjectsSlide Number 15Project SummariesAging Management of Dry Fuel Storage System ComponentsWelded Stainless Steel Canister Aging ManagementStainless Steel Canister Non-Destructive Examination Techniques and Delivery SystemsThrough-wall CISCC Consequence Analysis�New Project (Follow up to 2016 effort)Mitigation/Repair of Welded Stainless Steel Canisters�New Project – Not FundedUsed Fuel Integrity during Extended Storage and TransportationHigh Burnup Spent Fuel Data Project�(aka the HBU Demo)High Burnup Issues Resolution – Cladding Performance Criticality Control during Used Fuel StorageSpent Fuel Pool Criticality: Depletion Benchmarks for Full Burnup Credit ValidationNeutron Absorber Material DegradationNeutron Absorber Materials�New Project: Update of Neutron Absorber Material Handbook – Not FundedTechnical Basis for Disposal of Used Nuclear FuelProjects not Associated to a RFAExtended Storage Collaboration Program (ESCP)CFD Study of Partial SFP Drain Down�New Project – Not FundedAll Prioritization CommentsAging Management of Dry Fuel Storage System Components�CommentsUsed Fuel Cladding Performance during Extended Storage and Transportation�CommentsCriticality Control during Used Fuel Storage and Transportation�CommentsTechnical Basis for Disposition of Used Nuclear Fuel�CommentsFive-Year Plan�2017-2021Five-Year Plan: 2017-2021Extended Storage Goals and Trajectory (1/2)Extended Storage Goals and Trajectory (2/2)Criticality Goals and TrajectoryOther Potential Near-Term Projects/Project Areas (1/2)Other Potential Near-Term Projects/Project Areas (2/2)Slide Number 45

proposed 2017-2018 project portfolio · proposed 2017-2018 portfolio discussion of key u nfunded...

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