The complete and safe disposal of large irradiated graphite waste from nuclear reactors has
attracted worldwide attention. The core target for the treatment of irradiated graphite is to …

Abstract Beginning with Chicago Pile I, graphite has been used as a moderator material in
nuclear power stations and is considered a potential material for use in future Generation IV …

Raman spectroscopy has long been used in studying irradiation damage in carbon/graphite
materials. It is however unclear if the measurements from different types of materials are …

Three self-sintered graphite blocks (SGs) were prepared from green pitch cokes with
different average grain sizes (5.1, 3.1 and 1.9 μm) using cold isostatic compaction. The …

Microstructures of nuclear graphite have been investigated based on the analysis of both X-
ray diffraction patterns and High Resolution Transmission Electron Microscopy images …

Graphite has been a core structural material and neutron moderator since the first man-
made chain reaction experiment in Chicago. This article will discuss the requirements of …

Multiple length-scale microstructural characterisation has been conducted on four different
grades of unirradiated fine-grained graphite: CL 2020, IG 430, SGL R7650 and POCO ZXF …

A carbon-fibre reinforced carbon-matrix (C/C) composite was irradiated with 30 MeV C 6+
ions to a peak damage of∼ 25 dpa. Ion irradiation-induced microstructural changes were …

Abstract The USA DOE Advanced Reactor Technologies (ART) graphite R&D program
supporting HTR design is one of the longest running nuclear graphite R&D programs …

The irradiation behavior of graphite is essential for its applications in the nuclear industry.
However, the behavioral differences of graphite remain obscure because of the very limited …