19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor (8. 18-22, 2019 *Boston, MA, USA)

*Website: http://envdeg.ans.org/

The 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems- Water Reactor meeting is to foster an exchange of ideas about such problems and their remedies in water-cooled nuclear power plants of today and of the future. This meeting covers material problems facing nickel base alloys, stainless steels, pressure vessel & piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components & systems.

Schedule At A Glance

General Topics List

Accident Tolerant Fuel Cladding
Additive Manufacturing Applications/Progress
Advances in Materials Computational Modeling Supporting SCC and Fatigue Understanding
BWRSCC
BWR Water Chemistry
Cables and Concrete Aging and Degradation General SCC and SCC Modeling
IASCC Testing
Irradiation Damage ? Nickel Alloys Irradiation Damage ? Stainless Steels Irradiation Damage ? Swelling
Plant Operating Experience PWR Nickel SCC ? Initiation
PWR Nickel SCC ? Mechanistic Understanding PWR Nickel sec -Alloy 690
PWR Oxides and Deposits PWR Secondary Side
PWR Stainless Steel SCC and Fatigue Special Topics
Stainless Steel Aging and CASS
Welds, Weld Metal and Weld Assessments Zirconium and Fuel Cladding

Organizers

General Chair:
John H. Jackson (Idaho National Laboratory)

Program Chair:
Denise J. Paraventi (Naval Nuclear Laboratory)

Assistant Technical Program Chair:
Stuart L. Medway (Wood Material Science Laboratory)