Graphite components serve as structural support and as a neutron moderator in multiple
nuclear power stations and is also a prospective material in Generation IV reactor concepts …

Fiber-reinforced ceramic matrix composites are attractive for high-temperature nuclear
applications due to excellent thermal and mechanical properties as well as reasonable-to …

This paper concerns itself with predicting the failure of a full-size NBG-18 nuclear graphite
reactor component based only on test data obtained from standard tensile test specimens. A …

ABSTRACT A range of small scale, from centimetre scale to micrometre scale, mechanical
testing techniques have been used to measure the properties of nuclear reactor core …

The influence of bimodularity (different stress∼ strain behaviour in tension and
compression) on fracture behaviour of graphite specimens has been studied with fracture …

Super fine-grained graphite is a type of advanced nuclear graphite which was developed for
Molten Salt Reactor (MSR). It is necessary to establish a failure assessment method used for …

The full characterization of the physical and mechanical properties of candidate nuclear-
grade graphites is highly dependent upon an understanding of the distribution of values that …

Traditionally primary irradiation creep is introduced into graphite analysis by applying the
appropriate amount of creep strain to the model at the initial time-step. This is valid for …

This paper describes the process for approximating the optimal size of a link volume
required for weakest link failure calculation in nuclear graphite, with NBG-18 used as an …

High-purity graphite is the core structural material of choice in the Very High Temperature
Reactor (VHTR) design, a graphite-moderated, helium-cooled configuration capable of …