-
UKAEA-STEP-PR(24)012023
-
UKAEA-STEP-PR(24)032024
This paper sets the context for those that follow in this Special Edition by describing why STEP (Spherical Tokamak for Energy Production) has been launched, what it aims to achieve (benefits) and, principally, how the whole programme will be delivered (strategy). The paper draws on work on major project delivery and organisation design and ap…
-
UKAEA-CCFE-PR(24)062023
We describe the parameterization of a tungsten-hydrogen empirical potential designed for use with large-scale molecular dynamics simulations of highly irradiated tungsten containing hydrogen isotope atoms, and report test results. Particular attention has been paid to getting good elastic properties, including the relaxation volumes of small def…
-
UKAEA-CCFE-PR(24)052022
Effects of neutron irradiation on materials are often interpreted in terms of atomic recoils, initiated by neutron impacts and producing crystal lattice defects. We find that, in addition, there is a remarkable two-step process, strongly pronounced in heavy elements, involving the generation of energetic γ-photons in non-elastic collisions of n…
-
UKAEA-CCFE-PR(24)042023
A small, novel, integrated SHM system has been deployed during full-scale testing of a wing fatigue test and a fuselage pressurisation test. Complementary NDE measurement techniques were combined, with inputs from visible and infrared optical sensors, as well as resistance strain gauges. Sensor unitswere deployed at regions of interest and int…
-
UKAEA-CCFE-PR(24)032024
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
-
UKAEA-CCFE-CP(24)012022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
-
UKAEA-CCFE-PR(23)1912023
ITER is of key importance in the European fusion roadmap as it aims to prove the scientific and technological feasibility of fusion as a future energy source. The EUROfusion consortium of labs is contributing to the preparation of ITER scientific exploitation and operation and aspires to exploit ITER outcomes in view of DEMO. The paper provides …
-
UKAEA-CCFE-PR(23)1892023
The separation of hydrogen isotopes is a vital step in preparing tritium and deuterium fuels for future fusion energy plants. This represents a fundamental challenge to fusion energy since the separation process must be able to handle high throughputs of hydrogen isotopes with a low tritium inventory, as tritium is highly radioactive and hazardo…
-
UKAEA-CCFE-PR(23)1882022
In 2019, the JET-ILW was equipped with a Shattered Pellet Injector (SPI) system with a wide capability to allow studies on the efficacy of shattered pellets in reducing the electro-magnetic and the thermal loads during disruptions and the avoidance/suppression of the formation of runaway electrons. The fully commissioned system became operationa…
Showing 341 - 350 of 2527 UKAEA Paper Results