international materials research (imr)•irradiated materials testing and modeling of stainless...
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© 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
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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
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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.
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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
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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
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‘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.
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‘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
International,Domestic US
Or BothValue
Affected Guidance and
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.
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‘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
International,Domestic US
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.
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‘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
International,Domestic US
Or BothValue
Affected Guidance and
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.
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‘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
International,Domestic US
Or BothValue
Affected Guidance and
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.
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‘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.
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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.
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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.
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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.
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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
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Questions
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