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UKAEA-RACE-PR(25)052025
This paper presents a technical overview of AutoInspect, a ROS-based software system for robust and extensible mission-level autonomy. Over the past three years we have deployed AutoInspect on multiple platforms in a variety of environments, from forests to fusion reactors, for durations ranging from hours to weeks. The AutoInspect system combin…
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UKAEA-CCFE-PR(25)3382025
Tungsten-based BCC superalloys utilising coherent intermetallic strengthening offer a route to improved high temperature
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UKAEA-CCFE-PR(25)3372025
Most research reactors (RRs) in Europe are over 60 years old, and there are only limited efforts underway (e.g., PALLAS and JHR projects) to partially replace this aging infrastructure. Continued safe operation (CSO) of these reactors is crucial to sustaining the EU’s leadership in nuclear materials development and qualification for advanced r…
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UKAEA-CCFE-PR(25)3362025
A method for determining the fast-ion population density in magnetically confined plasmas as a function of pitch-radius, (λ, R), using a solid-state neutral-particle analyzer (ssNPA) signal and neutral-beam injection (NBI) power-output data has been developed. Oscillations in the NBI power output are replicated only in the active part of the ssN…
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UKAEA-CCFE-PR(25)3352025
The calibration of the JET x-ray spectrometer is presented. The absolute throughput, diffractor focussing and instrument function of the spectrometer is presented and the quality of the ion temperature measurement is re-assessed, particularly at the lower end. The addition of a second diffractor enables simultaneous measurements of the spectra …
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UKAEA-CCFE-PR(25)3342025
This study aims to systematically examine various methods leveraging machine learning (ML) to assimilate data for investigating thermal systems. These measured or observed data may include temperature or thermal material properties and could be synthetically (computationally) generated or experimentally obtained. The goal of these ML-augmented meth…
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UKAEA-CCFE-PR(25)3332024
The plasma-facing components of nuclear fusion reactors are continuously subjected to high thermal loads and bombardment by hydrogenic ions, resulting in erosion of the first-wall material and sputtering of atomic and molecular species into the edge plasma. The management of reactor component lifetimes and control of sputtered plasma impurities r…
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UKAEA-CCFE-PR(25)3322025
Lithium oxide is an important candidate material for tritium breeding in fusion nuclear reactors. Here we assess the disorder created in Li2O on bombardment by high-energy neutrons, examining the mechanisms of recovery and the…
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UKAEA-CCFE-CP(25)162023
Permeation of hydrogen isotopes, especially tritium, is expected to be a major challenge for future fusion reactors due to the high temperatures expected. Countless permeation experiments have been performed with the aim to study hydrogen permeation and permeation barriers, varying in many ways: the materials used, the experimental conditions under…
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UKAEA-CCFE-PR(25)3312025
The effect of different D2 fueling locations and divertor closure in the MAST-U is studied in detail with the SOLPS-ITER code to gain insights to detachment physics in H-mode plasma experiments in conventional divertor (CD) configuration. The SOLPS-ITER simulations for MAST-U H-mode plasma reveals that changing D2 fueling location significantly i…
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