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UKAEA-STEP-CP(24)032021
Uncertainty quantification is a vital part of all engineering and scientific pursuits. Some of the current most challenging tasks in UQ involve accurately calibrating, propagating and performing optimisation under aleatory and epistemic uncertainty in high dimensional models with very few data; like the challenge proposed by Nasa Langley this year.…
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UKAEA-CCFE-PR(24)2372021
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-IT…
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UKAEA-CCFE-PR(24)2332024
Starting from the assumption that saturation of plasma turbulence driven by temperature-gradient instabilities in fusion plasmas is achieved by a local energy cascade between a long-wavelength outer scale, where energy is injected into the fluctuations, and a small-wavelength dissipation scale, where fluctuation energy is thermalized by particle…
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UKAEA-CCFE-CP(24)122022
Modern nuclear physics software is well-validated, providing advanced capabilities to support the engineering of the future generations of fission and fusion reactors. Transport simulators can model the transport of neutrons through reactor geometries and inventory codes can accurately predict transmutation and activation. Meanwhile, material mo…
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UKAEA-STEP-PR(24)182024
This paper presents a comprehensive overview of the preliminary divertor design and plasma exhaust scenario for the reactor-class Spherical Tokamak for Energy Production (STEP) project. Due to the smaller size of the machine, with a major radius less than half that of most DEMO concepts, the current design features a double-null divertor geometr…
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UKAEA-STEP-PR(24)172024
Retention of hydrogen isotopes is a critical concern for operating fusion reactors as retained tritium both activates components and removes scarce fuel from the fuel cycle. Radiation-induced displacement damage in SiC may influence the retention of hydrogen isotopes compared to pristine SiC. Deuterium retention in neutron irradiated high purity…
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UKAEA-STEP-PR(24)162023
The STEP (Spherical Tokamak for Energy Production) fusion programme aims to produce net energy as a prototype fusion energy plant in the 2040s. To find an exhaust solution which is compatible with the core, we need to achieve high impurity enrichment. In this study, we investigated the impact of deuterium gas puff location on impurity enrichme…
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UKAEA-CCFE-PR(24)2362024
Inconel 625 is a nickel-chromium based super alloy used in the construction of the vacuum vessel of the Joint European Torus (JET) experimental fusion device. It was selected for its mechanical properties at elevated temperature, being exposed to vacuum baking at >300°C and heat loads of typically 0.5 MW/m2 for recessed areas of t…
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UKAEA-CCFE-PR(24)2342024
There is a rapidly growing demand for robotic RM systems which are able to support future nuclear applications currently in development. This paper covers the testing and verification of radiation hardened electronics via a representative test bench utilising components currently used in irradiated environments relevant to nuclear fission, nucle…
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UKAEA-CCFE-PR(24)2322024
The JET-ILW pure Tritium and Deuterium-Tritium (DTE2) experimental campaigns took place in 2021-2022. Tritium (T) and Deuterium-Tritium (D-T) operations present challenges not encountered in present day tokamaks [1]. This contribution focuses on Ion Cyclotron Resonance Heating (ICRH) operations in tritium and deuterium-tritium plasmas, starting …
Showing 281 - 290 of 2527 UKAEA Paper Results