18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

August 13–17, 2017 • Marriott Portland Downtown Waterfront • Portland, Oregon, USA


Technical Program

Here’s what past attendees are saying about this conference:
“The work presented has a high level of applicability to my current job.”
“The quality of the presentations at the conference are typically always of high quality.”

Keynote Speakers Announced

The 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors will bring together industrial and academic leaders from around the world for thought-provoking discussions on today's materials degradation problems. Keynote speakers include:

Todd Allen
Professor, University of Wisconsin, and Senior Fellow, Third Way
"21st Century Vision of Nuclear Energy"

Scot A. Greenlee
Senior Vice President, Engineering and Technical Services, Exelon Nuclear Generation
"The 21st Century Vision for Nuclear Energy—U.S. Industry Perspective"

A Tribute to Roger Washburne Staehle

A special session during the conference banquet led by Peter Andresen, Andresen Consulting, will honor Roger Washburne Staehle (February 4, 1934–January 16, 2017). An international giant in the field of metallurgy and corrosion, Staehle founded the Fontana Corrosion Center (FCC), in addition to holding positions at The Ohio State University and the University of Minnesota. Among many honors throughout his career, he most notably received the W.R. Whitney Award from NACE, was a Fellow of NACE International and The Electrochemical Society, and was elected to the National Academy of Engineering in 1978.


Technical Program Details

View the Environmental Degradation 2017 Sessions at-a-Glance:
Session Title Session Chair
Accident Tolerant Fuel Cladding Gary Was, University of Michigan
BWR SCC and Water Chemistry Bob Carter, Electric Power Research Institute
Cables and Concrete Aging and Degradation – Cables Leo Fifield, Pacific Northwest National Laboratory
Cables and Concrete Aging and Degradation – Concrete Thomas Rosseel, Oak Ridge National Laboratory
General SCC and SCC Modeling Raj Pathania, Electric Power Research Institute
IASCC Testing – Characterization Anders Jenssen, Studsvik Nuclear AB
IASCC Testing – Initiation and Growth Peter Andresen, Andresen Consulting
Irradiation Damage – Nickel Based and Low Alloy Mychailo Toloczko, Pacific Northwest National Laboratory
Irradiation Damage – Stainless Steel Larry Nelson, JLNelson Consulting
Irradiation Damage – Swelling Frank Garner, Radiation Effects Consulting
Plant Operating Experience Maria-Lynn Komar, Kinectrics Inc.
PWR Ni SCC – Initiation David Morton, Knolls Atomic Power Laboratory
PWR Nickel SCC – Aging Effects Tyler Moss, Naval Nuclear Laboratory
PWR Nickel SCC – Alloy 600 Mechanistic Steve Bruemmer, Pacific Northwest National Laboratory
PWR Nickel SCC – Alloy 690 Mechanistic Stuart Medway, Amec Foster Wheeler
PWR Nickel SCC – SCC Bogdan Alexandreanu, Argonne National Laboratory
PWR Oxides and Deposits Cecillie Duhamel, MINES ParisTech
PWR Secondary Side Ian De Curieres, IRSN
PWR Stainless Steel SCC and Fatigue – Fatigue Denise Paraventi, Naval Nuclear Laboratory
PWR Stainless Steel SCC and Fatigue – SCC Gabriel Ilevbare, Idaho National Laboratory
Special Topics I – Materials Pal Efsing, Ringhals AB
Special Topics II – Processes Ulla Ehrnsten, VTT Technical Research Centre of Finland Ltd.
Stainless Steel Aging and CASS Steve Fyfitch, Areva Inc.
Welds, Weld Metals, and Weld Assessments Catherine Guerre, CEA
Zirconium and Fuel Cladding Jacki Stevens, Areva Inc.

View or download the PDF registration flyer to share program information with your colleagues.

Abstract Submissions

The abstract submission site is now closed. We are no longer accepting abstracts. If you have any questions regarding abstract submissions, send an e-mail to TMS Programming Staff.

For insights into potential topic areas for abstracts, view the final programs from past Conferences on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors:

View the final programs from past World Congresses on ICME for examples of abstracts and technical topics presented at the congress:

For More Information

For more information about this meeting, please complete the meeting inquiry form or contact:

TMS Meeting Services
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