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UKAEA-CCFE-PR(25)2772021
In a snowflake (SF) divertor, two magnetic field nulls are placed close to each other, creating four strike points (SPs) compared to two in a standard X-point divertor. In preparation for MAST-U experiments, magnetic configurations with the standard and SF divertors with various locations and separation distances of the nulls were modeled using …
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UKAEA-CCFE-PR(25)2762024
Creep-fatigue damage has been recognised as a critical failure mode for high-temperature structures. In fusion power reactors, plasma-facing components endure complex loading conditions, resulting in high thermomechanical stresses. These components, often made from 316L material, joined to ferritic-martensitic steels, face significant challenges du…
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UKAEA-CCFE-PR(25)2752021
Several fusion power concepts propose the use of liquid lithium as the primary coolant and tritium breeder. Conventional Heat Exchangers (HEX) use water. In order to avoid tritium permeation into water, a molten salt can be used as secondary coolant, with water as the tertiary system. Nevertheless, the design of the HEX to transfer the energy fr…
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UKAEA-CCFE-PR(25)2742021
Efficient plasma core fuelling is a key issue for achieving steady-state scenarios in large magnetic confinement fusion devices. At present, the most promising technique to achieve this goal is the injection of cryogenic pellets. In this paper, the injection of nominal pellets into standard plasma scenarios in the tokamak ITER and the ste…
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UKAEA-CCFE-PR(25)2662024
This paper reports on a FEM-based computational methodology to assess dynamic amplification factors (DAF) of a divertor cassette, under electromagnetic (EM) impact loads caused by a plasma disruption event. The investigation concerns a typical divertor cassette body (CB) of the European DEMO reactor (baselin…
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UKAEA-CCFE-PR(25)2682023
In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure no production of neutrons from fusion reactions. With the expected higher L-H power threshold of hy…
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UKAEA-STEP-PR(25)282023
Generation of Runaway Electrons (REs) during plasma disruptions, and their impact on plasma facing components, is of great concern for ITER and future reactors based on the tokamak concept. Current STEP (Spherical Tokamak for Energy Production) concept design flat top operating point features a plasma current higher than 20 MA and thus any plasm…
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UKAEA-CCFE-PR(25)2692024
A linear-elastic computer simulation (model) for a single particle of TRISO fuel has been built using a bond-based peridynamic technique implemented in the finite element code ‘Abaqus’. The model is able to consider the elastic and thermal strains in each layer of the particle and to simulate potential fracture both within and between layers…
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UKAEA-RACE-PR(25)022024
Finding optimum kinematic designs for non-standard robotic manipulators, such as those used in medical, nuclear, and space applications is challenging due to the need to adapt to complex tasks within constrained environments. This design optimization problem is multi-dimensional and non-convex, with nonlinear constraints. Ensuring reachability, …
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UKAEA-CCFE-PR(25)2672024
The first generation of nuclear fusion reactors is expected to operate using a mixture of deuterium(D) and tritium(T) fuel. Controlling the D:T ratio is a promising option to control the fusion burn rate. The Joint European Torus (JET), as the only operational tokamak which can use tritium, is uniquely placed to test th…
Showing 271 - 280 of 2581 UKAEA Paper Results