Program

Categories

A. Development and qualification of structural materials for DEMO and beyond.

Ferritic/martensitic steels
Advanced and ODS steels
Ceramics, ceramic composites, and other low-Z materials
Tungsten, refractory alloys, and other high-Z materials
Novel highly radiation-resistant alloys

B. Materials for high heat flux plasmas facing components: divertor, limiter, first wall.

Plasma-facing materials
High heat-flux materials: heat-sink and structural application
Materials for limiters
Liquid metal divertors: material issues

C. Development and characterization of functional materials applied in blankets and other n-irradiation affected systems

Breeding and neutron multiplier ceramic materials
Coatings
Barriers, insulating materials and flow-channel inserts
Plasma-diagnostic system materials
First mirrors and auxiliary systems
Magnetic materials

D. Fusion-specific applications of materials, including environmental effects.

Tritium and deuterium: retention, accumulation, diffusion and release, including effects of irradiation
Concomitant hydrogen and helium embrittlement
Irradiation and coolant accelerated crack extension
Chemical compatibility: oxidation, corrosion, and environmental effects

E. Materials engineering and application including joining of similar or dissimilar materials.

Fabrication and materials engineering
Joining of similar and dissimilar materials: process optimization, properties and development of haracterization methods
TBM: material issues and technologies
ITER material technologies open issues

F. Qualification of irradiation effects in neutron sources, accelerators and other test systems including advanced characterization methods.

Intense fusion neutron sources for materials validation
Advanced and ODS steels
Approaches to best estimate irradiated materials engineering data combining databases and modeling ITER-TBM as irradiation test bed and model verification
Other neutron irradiation devices and test facilities
Advanced microscopy and characterization methods

G. Materials-design interface and interactions codes, standards, and standardization including SSTT.

Materials database development and material property handbooks
Advanced design methodologies and design criteria for future fusion facilities
Damage accumulation, interaction and critical failure modes
Development of test technologies towards standardization and norms including SSTT
Safety criteria and requirements

H. Fundamental studies of radiation effects: modeling and experimental validation.

Multi-scale approaches and design of radiation resistant materials
Defect production and microstructural evolution
Fundamental helium, hydrogen, and tritium effects

I. National fusion projects and private fusion activities.

J. Cross-cutting issues and synergism with materials applications in other large-scale projects or highly loaded systems.

Cross-cutting material issues for fusion and fission nuclear power systems
Synergies with material development in other energy research communities
Education and training

K. Ron Klueh Memorial.

Dr. Ronald Klueh, a retired materials scientist at Oak Ridge National Laboratory, passed away on March 23, 2024.
He was a pioneer in the field of RAFM steels for fusion applications and made significant contributions to ferritic/martensitic steel research.
A memorial session will be held to honor his achievements and emphasize the progress made through his works.

Registration Desk

JTB Corp, Western Japan MICE Branch
6F JTB Bldg. 2-1-25
Kyutaro-machi, Chuo-ku, Osaka 541-0056 Japan
E-mail: westec_op6@jtb.com