International Materials Research (IMR)•Irradiated Materials Testing and Modeling of Stainless Steels ... 12.1 Update the Materials Handbook for Nuclear Plant Pressure Boundary Applications

© 2019 Electric Power Research Institute, Inc. All rights reserved.w w w . e p r i . c o m

Mike BurkeTechnical Executive, IMR

Anne DemmaProgram Manager, IMR

EPRI-NRC Technical Exchange MeetingRockville, Md.May 15th, 2019

International Materials Research (IMR)Update – Status of Projects and Transition from PSCR to IMR

© 2019 Electric Power Research Institute, Inc. All rights reserved.w w w . e p r i . c o m2

Top Technical Issues • Irradiated Materials Testing and Modeling of Stainless Steels

– Participate in global research efforts to better understand the role of key parameters associated with IASCC and void swelling of reactor materials and develop improved materials for reactor vessel internals components for replacement in existing plants or for new plants

• Potassium Hydroxide Materials Testing– Perform materials testing to qualify potassium hydroxide to

potentially replace lithium hydroxide in certain PWR designs

• Environmentally Assisted Fatigue Testing and Modeling– Perform testing and develop models to more accurately predict EAF

in light water reactor environments for existing and new plantsIASCC Initiation Test Set-up


2018-19 Delivered ReportsTitle

Irradiation-Assisted Stress Corrosion Cracking of Ti-Stabilized Austenitic Stainless Steel: IASCC in VVER Reactor Environments

Progam on Technology Innovation: Toward Predictive Modeling and Mitigation of Irradiation Assisted Stress Corrosion Cracking of Austenitic Steels in LWR Core Components

Irradiation-Assisted Stress Corrosion Cracking (IASCC) Susceptibility and Evolution of Microstructure in Austenitic Alloys after Proton Irradiation: 2018 Interim Report

Materials Handbook for Nuclear Plant Pressure Boundary Applications (2018)

Evaluation of Microstructure and Performance for Alloy 600TT Steam Generator Tubing

Relevance of Long Range Ordering in Nickel-Chromium-Iron Alloys to Pressurized Water Reactors

Atom Probe Tomography Round Robin on Irradiated Stainless Steels

Characterization and of the Dilution Zone of Alloy 690/52/Carbon Steel Welds of CANDU Feeder Pipe Flow Elements

Crack Initiation of Alloy 600 in PWR Water

Also published the Materials Degradation Matrix, Revision 4 in 2018.


2019-2020 Plan with Materials RFAs & Projects (1/2)Materials RFA Title Project Title

#1 - Internals Management No current projects.#2 - Stainless Steel Alloys

2.1 Development of IASCC Data and Models for Ti Containing Stainless Steels in VVER2.2 Mechanistic Understanding of IASCC Failures in BWR Shroud2.3 Development of a Microstructural Database of Irradiated Stainless Steels and of Models that Link Microstructure and Materials

Performance2.4 Alloy Variability and IASCC Susceptibility in Stainless Steels2.5 Rapid Quantification of Irradiation Induced Microstructures by Deep Learning – Not funded to date2.6 Critical Stress for IASCC Initiation at Grain Boundaries2.7 Irradiation Effects on Stabilized Stainless Steels (IASCC, Void Swelling)2.8 Rapid Simulation of Void Swelling in Stainless Steels at High Fluence via Ion Irradiation of LWR Irradiated Steels2.9 Planning of Plant Materials Extraction

#3 - Nickel-base Alloys3.1 Grain Boundary Oxidation and Cohesive Strength of Oxidized Grain Boundaries of Alloy 600/600TT in PWR Environment3.2 Characterization of the Dilution Zone of Alloy 690/52/Carbon-Steel Welds of CANDU Feeder Pipes3.3 Investigate Applicability of LRO of Alloy A690 to LWR Components

#4 Low Alloy Steels4.1 Impact of Carbon on Mechanical Properties of Low Alloy Steels4.2 Containment Liner Plate Corrosion Modeling


2019-2020 Plan with Materials RFAs & Projects (2/2)Materials RFA Title Project Title#5 - Fatigue

5.1 Investigate Short Crack Behavior in EAF of Stainless Steel5.2 EAF Prototypical Full Component Test (Co-funded)

#6 – Wear No current projects.#7 - Flow Phenomena No current projects.#8 - Water Chemistry and Mitigation

8.1 Testing of Irradiated Materials in Support of a Plant Demonstration of KOH for PWR Primary pH Control8.2 Testing of Unirradiated Materials in Support of a Plant Demonstration of KOH for PWR Primary pH Control

#9 - Repair and Fabrication

9.1 Technical Concepts and Viability Assessment of Direct Additive Manufacturing for ChemicallyUniform Large Wrought Components of NPPs

#10 - New Alloy Development10.1 Advanced Radiation Resistant Materials (ARRM) Phase 1 -- Completion10.2 Advanced Radiation Resistant Materials (ARRM) Phase 2 -- Neutron Irradiation

#11 – Inspection No current projects.#12 - Database, Training and Tech Transfer

12.1 Update the Materials Handbook for Nuclear Plant Pressure Boundary Applications in 2018;12.2 Update the Materials Information portal with the revised MDM and Materials handbook.12.3 Generate CBT Trainings on PSCR Related Subjects


‘Big Picture’ Update for the Rapid Simulation of Void Swelling in Stainless Steels Using Ion Irradiation

Applicability

RFA Title 2019-2020 Project Number

Sche

dule Project

IMT Gaps and

Priority Com

pone

nts

International,Domestic US

Or BothValue

Affected Guidance and

Direct or Indirect Inputs

from the Project into

the Guidance

MRFA 2: Stainless

Steel Alloys

2.8-Rapid Simulation of

Void Swelling in Stainless Steels at High Fluence

via Ion Irradiation of

LWR Irradiated Steels

2016-2021

P-AS-14a (H),

P-AS-14b (H),

P-AS-15 (M)

PWR and VVER reactor

internals.Both

This data will contribute to validating cluster dynamics

void swelling models in MRP-391 and improve the

capability to predict void swelling in a time and cost

efficient method. The validated model would be

incorporated in MRP-211 and MRP-135 that are supporting

documents to MRP-227.

MRP-391; MRP-211;

MRP-135 and MRP-227. Indirect Inputs.

• Materials was shipped from Sweden to the USA in 2018 and testing started. Project on track to be completed in 2021.


‘Big Picture’ Update for Impact of Carbon on Mechanical Properties of Low-Alloy Steels

Applicability

RFA Title 2019-2020

Project Number Sc

hedu

le Project IMT Gaps

and Priority Co

mpo

nent

s


Or BothValue


Direct or Indirect Inputs from the Project into the

Guidance

MRFA 4: Low Alloy

Steels

4.1-Impact of Carbon on Mechanical

Properties of Low Alloy

Steels

2018-2020

P-AS-47 (H),

P-AS-49 (H),

P-AS-45 (M)

International and domestic existing LWRs as well as

new LWRs currently being

built such as the EPR® and

AP1000® designs.

Both

This research will provide robust

quantitative data on the effects of carbon on the toughness of low alloy steel over

the range of 0.18 wt.% to 0.4 wt.% C.

EPRI’s assessment of

the safety significance of high carbon for integrity (MRP-

417, Rev. 1).

• Plan is to complete the project in 2020 and we are on track. Contract in place and fabrication of the synthetic ingots performed.


‘Big Picture’ Update for EAF Component TestingApplicability

RFA Title 2019-2020

Project Number Sc

hedu

le Project IMT Gaps

and Priority Co

mpo

nent

s


Or BothValue

Affected Guidance and Direct or

Indirect Inputs from the Project into the

Guidance

MRFA 5: Fatigue

5.2-EAF Component

Testing

2018-2022

P-AS-02 (H),

B-AS-07 (H)

BWR and PWR EAF

Critical Components in operating

and new Plants.

Both

Results from this EAF Component testing will be used as the technical basis

for an improved methodology for

calculating CUF to meet EAF requirements for life

extension and new plants.EAF is a life limiting factor for some plants. This is a

highly leveraged collaboration project.

NRC NUREG/CR-6909;

Reg guide 1.207; ASME Code Case N-

809;RPP (Rule in

probation phase) n°3 of RCC-M

édition 2016 : "RPP n°3 – RCC-M ed. 2016" in France. Indirect Inputs.

• Plan is to complete the project in 2022 and we are on track.


‘Big Picture’ Update for Materials Testing for KOH Qualification

• Plan is to complete the project in 2020 and we are on track. • There is a KOH Advisory Committee in place with members with Chemistry, Materials and Fuel expertise.

Applicability

RFA Title 2019-2020

Project Number Sc

hedu

le Project IMT Gaps

and Priority Co

mpo

nent

s


Or BothValue


Direct or Indirect Inputs

from the Project into the

Guidance

MRFA 8: Water

Chemistry and

Mitigation

8.1 and 8.2-Testing of

Irradiated and UnirradiatedMaterials in Support of a

Plant Demonstration of KOH for PWR

Primary pH Control

2017-2020

P-AS-11 (H)

P-AS-12 (H)

PWRs plants

interested in switching from LiOH

to KOH chemistry

for PH control.

Both

The results of this project will ascertain whether KOH will cause

damage to structural materials of the reactor. If the results indicate that

KOH is no more damaging than LiOH, the plant demonstration of KOH in 2021 can move forward. Guidance

changes for using KOH instead of LiOHwill be incorporated in the EPRI report 3002000505. This supports a Nuclear Sector Strategic Initiative for a more reliable supply and a cost savings per

PWR unit per year of ~$100k.

PWR Primary Water Chemistry

Guidelines; Revision 7,

Volumes 1 and 2 (3002000505). Direct Inputs.


‘Big Picture’ Update for Advanced Radiation Resistant MaterialsApplicability

RFA Title 2019-2020

Project Number Sc

hedu

le Project IMT Gaps and Priority

Com

pone

nts


Or BothValue


Direct or Indirect Inputs from the Project into the

Guidance

MRFA 10: New Alloy

Development

10.1 and 10.2-

Advanced Radiation Resistant Materials (ARRM):

Phase 1 and Phase 2

2013-2018 for

Phase 1 and

2019-2025 for

Phase 2

P-AS-14a (H),

P-AS-14b (H),

P-RR-08 (M),

B-AS-26 (H),

B-AS-11 (M)

PWR, BWR, VVER and

CANDU irradiated

reactor internals in

operating and new plants.

Both

The use of advanced radiation resistant materials developed under this program will allow

utilities to operate their reactors with greater efficiency as well as lower maintenance, inspection

and repair costs. The recommendations for advanced

radiation resistant materials will be incorporated in industry repair

and replacement guidance, such as BWRVIP-84. This is a highly

leveraged collaboration project.

BWRVIP-84. Direct Inputs.

• During Phase 1 of the project, we selected promising alloys suitable for Phase 2; Report for Phase 1 completed in 2019. • Applying for NSUF funding for Phase 2 (Neutron Irradiation and PIE) this year.


‘Big Picture’ Update for Database, Training and Materials Strategic Tools

Applicability

RFA Title 2019-2020 Project Number

Sche

dule Project IMT

Gaps and Priority

Value

Affected Guidance and Direct or

Indirect Inputs from the Project

into the Guidance

MRFA 12: Database,

Training and Technology

Transfer

12.1 Update the Materials Information Portal with the

Revised MDM and MHB12.2 Generate CBT Trainings

on PSCR Related Subjects 12.3 Update the Materials

Handbook for Nuclear Plant Pressure Boundary

Applications

2018-2020 Both

Improved understanding of: Materials information for evaluation of important structural components in plants, with the focus on pressure

boundary components. Knowledge gaps associated with

degradation phenomena that may detrimentally affect reactor operation, reactor safety, or

regulatory climate; and the status of R&D needed to resolve the

knowledge gaps.

Direct inputs to: EPRI Materials Degradation

Matrix; Materials Handbook and PWR and BWR

Issue Management Tables.

• Plan is to complete the projects in 2020 and we are on track.


Government Proposals and Awards Update DOE National Scientific User Facility (NSUF) award received on 8/16/2018 for Rapid Simulation

of Void Swelling at Michigan Ion Beam Laboratory, which is a Partner Facility of the NSUF providing access to the capabilities of the laboratory.

DOE NEUP (Nuclear Energy University Programs) award received on 6/18/2018 for“Development of Corrosion Resistant Coatings and Liners for Structural Materials for Liquid Fueled Molten Salts Reactors” which aims to expand the application of EPRI-developed Moly-related technology (HIP, Welding, Multilayer material design, etc.) to the next generation nuclear concepts.

Completed the pre-application phase of NSUF FOA with a request for NSUF facilities for the Advanced Radiation Resistant Materials (ARRM) Phase 2 to access Neutron Irradiation facility.

DoE Advanced Reactors Program award received 2/28/2019 for Versatile Test Reactor Research and Development Phase Experiment Vehicle Development and Design.

Submitted an EPRI proposal to DOD in Q4 of 2018 for National Defense Stockpile Research Defense Logistics Agency (DLA) Strategic Materials BAA No.: BAA-DLASM-2018-01 Titled Qualification of Potassium Hydroxide (KOH) for Primary Coolant pH Control in Western-Design Pressurized Water Reactors. DoD response received March 6 and proposed a 1.2/1.0 cost share.


PSCR Transition to IMR – Update (1/2) The Announcement about the PSCR transition to IMR is on the PSCR

cockpit. In order to gain efficiencies in materials program engagement while increasing

focus on international utility member needs, EPRI sunsetted the Primary Systems Corrosion Research (PSCR) program and created a committee titled International Materials Research (IMR).

The mission of IMR, similar to PSCR, is to understand and address materials issues of global importance through materials testing, characterization, and associated modeling.

The IMR committee will meet during the Nuclear Power Council week and all International Nuclear Sector members are invited to participate.

U.S. members will continue to engage in the other programs, as appropriate, including BWRVIP, MRP and SGMP. The IMR staff will also continue to support these programs.

The projects prioritized under PSCR for 2019-2020 will continue as planned.


PSCR Transition to IMR – Update (2/2) Coordination with other Nuclear Sector Programs

– The IMR Staff will continue to coordinate and integrate research projects with other groups in the Nuclear Sector and continue to provide support to these groups in technical expertise and project management as needed.

– The PSCR Committee operated until December 31, 2018. The IMR Committee started January 1, 2019. Sunsetted PSCR – in December 2018

– Webcast was held with the PSCR members in November 2018.– EPRI Staff answered questions from members about the transition and followed-up with calls/emails.– Follow-up with first IMR Meeting at NPC in January 2019.

January Announcement about the PSCR cockpit. – The Primary Systems Corrosion Research (PSCR) Program is no longer active, effective as of January

2019. However, the PSCR cockpit is being maintained temporarily while we complete the transition from the PSCR cockpit to other webpages/cockpits.

IMR Communication Plan– First meeting held at NPC Meeting January 2019 – Committee objectives and structure outlined, Chair

and Vice-chair nominated.– IMR Staff will attend Q2 BWRVIP, MRP, SGMP, and ANT meetings.– Plans for Webinar June/July 2019. Committee meeting at NPC in Austin, Texas in August 2019.


International Materials Research (IMR) PlansPlans for 2019-2020

Continuation of existing planned projects to address IMT gaps Delivery of project deliverables Integration of IMR Projects related to BWRs, PWRs into BWRVIP,

MRP, SGMP Prioritizations and Strategic Plans Identification of International members related projects,

especially VVER and CANDUs


Questions

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Documents

International Materials Research (IMR)•Irradiated Materials Testing and Modeling of Stainless Steels ... 12.1 Update the Materials Handbook for Nuclear Plant Pressure Boundary Applications