MiNES 2019

American Nuclear Society ANS

MiNES is a new conference created to serve the fission reactor materials community that grew out of, and supplants, biannual symposia held at the TMS meeting (Microstructure Processes in Irradiated Materials – MPIM) and the ANS meeting (Nuclear Fuel and Structural Materials – NFSM). As such, the coverage of MiNES includes those topics held previously at MPIM and NFSM, which include the following:

Irradiation Damage

Irradiated Microstructures

Mechanical Properties of Irradiated Materials

Radiation Effects Simulation & Evaluation Techniques

Integrated Phenomena in Reactor Materials

Advanced Alloys and Materials for Nuclear Systems

Advanced Fuels & Actinide Materials

Nuclear Fuel Cycles

MiNES will be held biannually (every other year) in the autumn season with the first meeting to be held October 6-10, 2019 in Baltimore, MD, USA. ANS and TMS alternate sponsorship of the conference and assist an organizing committee headed by three conference chairs in planning the content and venue for each meeting. While held in the U.S., the organizers of MiNES strongly encourage international participation.

Technical Program

Irradiation Damage

Fundamental science of the irradiation damage process

Methods for quantifying and/or measuring irradiation damage

Role of boundaries and interfaces

Irradiated Microstructures

Microstructure evolution in metals and alloys

Irradiated microstructures in ordered ceramics, graphite, etc.

Novel methods for characterizing irradiated microstructures

Mechanical Properties of Irradiated Materials

Experimental and computational studies of irradiation effects on mechanical properties

Novel methods for evaluating mechanical properties of irradiated materials

Structure-property relationships in irradiated materials

Radiation Effects Simulation & Evaluation Techniques

Advancements in computational methods for simulation of irradiation damage

Experiment-model coupling and benchmarking 

Integrated Phenomena in Reactor Materials

Co-evolution of microstructural features

Emulation of neutron irradiation damage with ions 

Advanced Alloys and Materials for Nuclear Systems

Novel methods for processing and manufacturing

Development of irradiation-tolerant materials

Irradiation effects in advanced manufactured materials

Advanced Fuels & Actinide Materials

Novel fuel designs, their microstructures and properties

Irradiation effects on advanced fuel concepts

Microstructures and mechanical properties of actinide materials

Nuclear Fuel Cycles

Irradiation-related concerns and effects on spent fuel storage materials

Structure-property relationships in waste forms

More Information / Apply Now

Start Date

End Date

Type

Conferences

North%20America%2C%20La%20Grange%20Park%2C%20United%20States

North America

La Grange Park , United States

Start Date:

End Date:

Location

United States

La Grange Park

Type

Conferences

North%20America%2C%20La%20Grange%20Park%2C%20United%20States