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UKAEA-CCFE-PR(26)4542024
A fast neutral lithium beam is used at JET for more than 30 years to measure profiles of electron density in the pedestal and scrape off layer. The diagnostic was not designed for tritium operation. In this paper, we describe the modifications which were required to allow operation in tritium (T) and deuterium-tritium (D-T ) fuelled pulses at JE…
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UKAEA-CCFE-PR(26)4532024
Experimental campaigns at the Joint European Torus with an ITER-like Be/W wall (JET-ILW) with pure deuterium (D), tritium (T) and Deuterium-Tritium (DT) were a unique opportunity to explore various aspects related to the ITER operation. It should also be emphasized that the JET campaign at the end of 2021 included the first tokamak experiments u…
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UKAEA-CCFE-PR(26)4522024
Alloy X-750 was exposed to a 480 °C CO-CO2 reducing gas mixture at an oxygen partial pressure below the NiO dissociation pressure. Post-exposure analytical transmission electron microscopy (ATEM) analysis confirmed the occurrence of preferential intergranular oxidation (PIO) and internal oxidation which resulted in the formation of N…
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UKAEA-STEP-PR(26)092024
The Spherical Tokamak for Energy Production (STEP) programme hypothesises that a compact machine offers a route to reduced capital cost that directly tackles the barrier to entry of this potentially transformative technology. History has shown that with an unsolved, complex, and highly interdependent design challenge, there is a need to balance …
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UKAEA-STEP-PR(26)082024
The STEP (Spherical Tokamak for Energy Production) programme aims to deliver a first-of-a-kind fusion prototype powerplant (SPP). The SPP plasma places extreme heat, particle, and structural loads onto the Plasma Facing Components (PFCs) of the divertor, limiters, and inboard and outboard sections of first wall. The PFCs must manage the heat and…
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UKAEA-STEP-PR(26)052024
STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, including integrated core plasma modelling, MHD stability a…
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UKAEA-CCFE-PR(26)4512024
An understanding of the behaviour of the D or He fuel used in tokamak discharges is essential in analyses such as modelling edge and divertor transport and the erosion of the vessel walls. However, poor agreement is found between measurements made on the JET tokamak and collisional-radiative models used …
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UKAEA-STEP-CP(26)012024
The Spherical Tokamak for Energy Production (STEP) programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. The conceptual design of such a prototype, meeting engineering and physics constraints, is complex due to the tight aspect ratio and limited space in compact spheri…
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UKAEA-RACE-PR(26)112024
We consider planning problems where a robot must gather reward by completing tasks at each of a large set of locations while constrained by a time bound. Our focus is problems where the difficulty of each task, and thus its duration, can be predicted, but is not fully known in advance. We model difficulty-aware problems as a Markov decision proc…
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UKAEA-RACE-CP(26)032024
The primary objective of this work is to research, design, and draft an open standard for nuclear robotics, aiming to standardise the design, development, integration, interoperability, and overall through life capability management of technologies, devices, and platforms for robotic systems used in nuclear fusion and decommissioning operations.…
Showing 21 - 30 of 2581 UKAEA Paper Results