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07 - Imr Update August 2021
	ML21217A256
Person / Time
Issue date:	08/10/2021
From:	James Smith; NRC/NRR/DNRL
To:	;
	Hiser A
Shared Package
ML21217A247	List: ML21217A251; ML21217A252; ML21217A256; ML21217A257; ML21217A259; ML21217A260; ML21217A261; ML21217A262; ML21217A263; ML21217A302; ML21217A303; ML21217A304; ML21218A068; ML21221A124;
References
	Download: ML21217A256 (16)
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International Materials Research (IMR)

IMR Program Objectives The IMR Program enhances the understanding of the damage mechanisms in materials used in light and heavy water reactors. Research results lead to improved predictive models, more radiation-resistant materials, and potential countermeasures that contribute to the safe, continued operation of plant components.

IMR collaborates with other EPRI materials-related research programs, the Materials Aging Institute (MAI) at EDF, the U.S.

Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (US NRC), and international organizations to ensure that research projects and results reflect a wide range of nuclear technologies, operating conditions, and service environments.

IMR is also actively involved in internal and external programs that support the identification and qualification of materials for advanced reactors, including non-light-water reactors.

International Materials Research (IMR) - IMR Team Jean Peter Cem Morgan Smith Chou Topbasi Saucier Vacant Program Manager Principal Senior Technical Principal Technical Leader Technical Leader Assistant II Technical Leader jmsmith@epri.com pchou@epri.com ctopbasi@epri.com msaucier@epri.com 650-855-8775 650-855-2137 650-855-8902 704-595-2466 Chicago, IL Palo Alto, CA Palo Alto, CA Charlotte, NC

IMR Program Strategy

Lead for MRFAs 3, 4, & 8

Lead for MRFAs 2 and 12

IMR Program Support

Lead for MRFAs 9 and 10

Materials Aging

Environmentally-

Advanced Material

Communications IMTs and MDM Institute (MAI) Liaison Assisted Cracking Characterizations

Meeting Coordination

Support for MRFA 2

Lead for MRFA 5

Irradiated Materials

Irradiated Materials Testing

Materials for Gen IV

Irradiated Materials Testing

Nuclear Fuel Materials Reactors Research

Atom Probe

Advanced Reactor

Failure Analysis Tomography Materials 3 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

IMR Committee and Interest Groups IMR Leadership Team Exec. Sponsor: Henric Lidberg (Vattenfall)

Chair: Otto Yong (OPG)

Vice Chair: Vacant*

Program Manager: Jean Smith (EPRI)

François Foct (EDF) recently moved to a new position within EDF and resigned as IMR Chair 4 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

Materials Research Focus Areas (MRFAs)

BWRVIP, MRP, SGMP, and IMR use the same MRFAs to help identify common areas of research and to show correlation to Issue Management Table gaps.

MRFA 2: Stainless Steel Alloys Objective

Perform research activities focused on the impact of degradation mechanisms, environments, and fabrication on the material properties of stainless steel alloys. Investigations include work to develop, improve and/or expand applicability of currently available methodologies necessary to analyze, mitigate, and prevent phenomena that may impact the integrity of components composed of stainless steel alloys.

2021 IMR Projects

2.1 IASCC and Microstructural Modeling of Stabilized Steels

2.2 Mechanistic Understanding of IASCC Failures in BWR Shroud

2.3 Development of a Microstructural Database of Irradiated Stainless Steels and of Models that Link Microstructure and Materials Performance

2.4 Alloy Variability and IASCC Suceptibility in Stainless Steels

2.5 Rapid Quantification of Irradiation Induced Microstructures by Deep Learning

2.6 Critical Stress for IASCC Initiation at Grain Boundaries

2.7 Irradiation Effects on Stabilized Stainless Steels (IASCC, Void Swelling)

2.9 Planning of Plant Materials Extraction

2.10 Laser Annealing for Mitigation of IASCC Initiation 7 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

MRFA 3: Nickel-Based Alloys Objective

Perform research activities focused on understanding and managing the degradation mechanisms that affect nickel-based alloys in LWR environments. Investigations include understanding the role of fabrication processes on material properties; developing, improving, and/or expanding applicability of inspection, repair, and mitigation methodologies; and improving capabilities to analyze phenomena that may impact the integrity of nickel-based alloy components.

2021 IMR Projects

3.1 Characterization of Alloy 600/600TT Grain Boundaries in PWR Environments

3.3 LRO of Alloy 690 in LWR Components

3.5 Role of GB Carbides on Crack Initiation in Alloy 600 and Alloy 182 8 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

MRFA 4: Low Alloy Steels Objective

Research activities focus on the impact of degradation mechanisms, environments, and fabrication processes on the material properties of low alloys steels. Investigations include work to develop, improve and/or expand applicability of currently available methodologies necessary to analyze, mitigate, and prevent phenomena that may impact the integrity of components composed of low alloy steels.

2021 IMR Projects

4.1 Impact of Carbon on Mechanical Properties of Low Alloy Steels

4.3 Characterization of Environmentally-Assisted Cracking in CANDU Low-Alloy Steel Components 9 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

MRFA 5: Fatigue Objective

Develop and improve analytical methods and perform testing that can evaluate components undergoing degradation from fatigue. Investigate methodologies to determine fatigue susceptibility and identify mitigation and failure prevention options for nuclear plant components subject to fatigue.

2021 IMR Projects

5.1 Investigate Short Crack Behavior in EAF of Stainless Steel

5.2 EAF Component Test 10 www.epri.com © 2021 Electric Power Research Institute, Inc. All rights reserved.

MRFA 8: Water Chemistry and Mitigation Objective

Evaluate, develop, demonstrate, and implement effective technologies to mitigate material degradation and maintain effective water chemistry. Activities include research into water chemistry parameters, development and maintenance of guidance and investigations into phenomena that can alter the water chemistry of primary systems.

2021 IMR Projects

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

8.2 Testing of Unirradiated Materials in Support of a Plant Demonstration of KOH for PWR Primary pH Control

8.3 Development of More Rugged ECP Probe for BWRs

MRFA 9: Repair and Fabrication Objective

Development and improvement of fabrication and repair processes, guidance and technologies to repair nuclear plant components impacted by materials degradation phenomena and/or construct new and replacement components.

2021 IMR Projects

9.1 Additive Manufacturing for Large Forgings

MRFA 10: New Alloy Development Objective

Investigate alloys that are in use or have the potential for use in nuclear plant applications. Research is used in development of new methods, guidance and technologies to fabricate, evaluate, inspect and test alloys that have historically not been used or used in limited application in nuclear facilities.

2021 IMR Projects

10.2 Advanced Radiation Resistant Materials (ARRM) Phase 2 -- Neutron Irradiation and Post-Irradiation Testing

10.3 AI: Materials Qualification for Next-Generation Reactors

MRFA 12: Databases, Training, and Tech Transfer Objective

Develop and maintain databases, data collection and analysis tools, and knowledge transfer capabilities. Tasks include the collection, curation, and appropriate dissemination of plant data and operating experience, research results, and program information.

2021 IMR Projects

12.1 Annual Materials Handbook Revision

12.3 Computer-based Training for IMR Products

12.4 Interactive Materials Handbook

12.5 Issue Management Tables for VVER/CANDU

IMR DOE Rapid Turnaround Experiments TEM Characterization of IASCC Mechanical Testing of Irradiated Type 304 Type 304 core shroud material (2.1 - 3.4 dpa) Type 304 baffle plate material (~20 dpa) from a from a BWR plant decommissioned PWR was used for IASCC CGR Some tensile specimens were post-irradiation testing in the KOH qualification program.

annealed (PIA) at 553 °C for 60.7 minutes to - During testing, abrupt changes in CGR were detected remove radiation-induced defects in the grain by DCPD and attributed to the branched nature of intergranular cracks.

interior but retain RIS at grain boundaries TEM characterizations to compare as-irradiated Crack imaging using x-ray tomography and and PIA microstructures and previous testing neutron tomography to characterize crack environments (oxidizing; reducing) morphology and correlate to DCPD output.

Investigate the correlation between radiation- Investigate the feasibility of using these NDE induced microstructural changes and mechanical techniques for examining cracks in highly-behavior to provide insight to IASCC mechanisms irradiated samples.

ML21217A256

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