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UKAEA-CCFE-CP(23)562019
An important area of research required for fusion reactor design is the study of materials under high energy neutron irradiation. Deuterium-Tritium (D-T) reactions release 14.1 MeV neutrons and material studies of such high energy neutrons focusing on transmutation and activation are paramount for fusion tokamak devices such as ITER and DEMO. Th…
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UKAEA-CCFE-CP(23)552019
Cooling water in the primary circuit in both fission and fusion nuclear reactors is unavoidably exposed to neutrons leading to the generation of problematic short-lived isotopes, most importantly, 16N (T1/2=7.3s) via the 16O(n,p)16N reaction. This presents a significant itinerant radiation source to consi…
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UKAEA-CCFE-PR(23)1152023
This article starts with a brief description of two new viewing systems with a light path which crosses the biological shield wall and are compatible with Deuterium-Tritium (D-T) operations in JET. However, it focuses on the optical modelling and engineering design of one of them which is a multiple camera system producing a wide angle view (WAV)…
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UKAEA-CCFE-CP(23)522022
An investigation was conducted into minimising effective dose to members of the public in the unlikely event of an accident by optimising design parameters and site locations of future fusion power plants. This is part of our defence in depth approach for tritium safety that also includes significant work on the prevention of accidents. Calculat…
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UKAEA-CCFE-CP(23)502022
Global research programmes seeking to achieve a commercially viable model of a fusion power plant are being accelerated at an unprecedented rate. One critical element to the design and licensing is an accurate understanding of the radiation environment throughout the plant lifetime and subsequent decommissioning phase. The radiation field which res…
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UKAEA-CCFE-PR(23)1102022
The realisation of fusion energy depends on the development of advanced materials for challenging environments. Rapid screening of prototype alloys using magnetron sputtering and high throughput characterisation is currently being applied to candidate W alloys with improved mechanical performance, reduced activation and tolerance to damage from neu…
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UKAEA-STEP-CP(23)092022
The UK Spherical Tokamak for Energy Production (STEP) program is currently progressing the conceptual engineering design of a Spherical Tokamak-based fusion reactor. The program includes a project concerned with design of the reactor breeding blanket. The objective of this work was to develop a low fidelity, integrated simulation approach to sup…
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UKAEA-CCFE-CP(23)462022
Accurate and consistent measurements of the electron temperature (Te) profile are paramount for current fusion experiments, like JET, and future devices, such as ITER. In high performance plasmas in JET and TFTR, electron cyclotron emission (ECE) measurements for central Te>5 keV were systematically found to be up to 20%…
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UKAEA-CCFE-CP(23)442022
Due to their relatively higher Vbeam/VAlvén ratio, spherical tokamaks are ideal to investigate high-frequency modes such as Compressional Alfvén Eigenmodes (CAEs) and Global Alfvén Eigenmodes (GAEs), and so they have been previously studied in MAST [1, 2]. Besides, the recently installed scintillator-based Fast-Ion Loss …
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UKAEA-STEP-CP(23)082022
Microinstabilities often result in turbulence that influences energy confinement in tokamak discharges. One such microinstability, of particular importance to the design of next-generation spherical tokamaks (STs) such as STEP [1], is the microtearing mode (MTM), a tearing-parity mode centred on high-order rational surfaces. MTMs are short-wavel…
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