A.R. Raffray

Modeling of plasma hydrogen isotope behavior in porous materials (graphites/carbon—carbon composites)

An overview of safety and environmental considerations in the selection of materials for fusion facilities

Materials effects and design implications of disruptions and off-normal events in ITER

A New Approach for Assessing the Required Tritium Breeding Ratio and Startup Inventory in Future Fusion Reactors

Hydrogen isotope retention in beryllium for tokamak plasma-facing applications

Current status and critical issues for development of SiC composites for fusion applications

Research of the shielding effect and radiation resistance of composite CuBi2O4 films as well as their practical applications

Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials

Assessment and selection of materials for ITER in-vessel components

Structural materials for fission & fusion energy

Mechanical Properties of β-SiC After Si- and Dual Si + He-Ion Irradiation at Various Temperatures

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Assessment of erosion and tritium codeposition in ITER-FEAT

Exergy recovery during LNG regasification: Electric energy production – Part one

Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences

The influences of irradiation temperature and helium production on the dimensional stability of silicon carbide

Handbook of SiC properties for fuel performance modeling

On the thermal stability of the nanostructured tungsten coatings

LNG: An eco-friendly cryogenic fuel for sustainable development

High Temperature Ion-Irradiation Effects on Microstructural Evolution in β-SiC

Structural and Optical Properties of Silicon Carbide Powders Synthesized from Organosilane Using High-Temperature High-Pressure Method

Promise and challenges of SiCf/SiC composites for fusion energy applications

Neutron irradiation effects on plasma facing materials

Effects of irradiation and post-irradiation annealing on the thermal conductivity/diffusivity of monolithic SiC and f-SiC/SiC composites

Influence of carbon precursors on thermal plasma assisted synthesis of SiC nanoparticles

Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Mistral: A comprehensive model for tritium transport in lithium-base ceramics

Breeding blanket concepts for fusion and materials requirements

RACLETTE: a model for evaluating the thermal response of plasma facing components to slow high power plasma transients. Part I: Theory and description of model capabilities

Progress in tritium retention and release modeling for ceramic breeders

High performance blanket for ARIES-AT power plant

Armour Materials for the ITER Plasma Facing Components

Progress in tritium retention and release modeling for ceramic breeders

Design and material issues for high performance SiCf/SiC-based fusion power cores

Critical heat flux analysis and R&D for the design of the ITER divertor

As assessment of models of tritium release from ceramic breeders for blanket analysis applications

Modeling of tritium release from beryllium in fusion blanket applications

RACLETTE: a model for evaluating the thermal response of plasma facing components to slow high power plasma transients. Part II: Analysis of ITER plasma facing components

An Assessment of the Brayton Cycle for High Performance Power Plants