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UKAEA-CCFE-PR(21)172020
The accurate modelling of the activation of flowing material in a fusion reactor, such as coolant water or lithium-lead breeder, has important safety and shielding implications. Two codes developed at UKAEA which account for neutron flux variation have been investigated for the potential for incorporating computational fluid dynamics (CFD) and c…
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UKAEA-CCFE-CP(20)1242020
During ITER operations the water coolant flowing through components such as the first wall, blanket modules, divertor cassettes and vacuum vessel will become activated by high energy neutrons. Two key neutron-induced reactions will occur with oxygen in the water producing the radioactive isotopes, N-16 and N-17, which have relatively short half-liv…
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UKAEA-CCFE-CP(20)1082020
In future fusion power plants, such as DEMO, D-T neutron emission is predicted to exceed 1×1021 neutrons/second. Accurately monitoring neutron energies and intensities will be the primary method for estimating fusion power, and calculating key parameters, including the tritium breeding ratio and nuclear heating. The Novel Neutron Det…
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UKAEA-CCFE-CP(20)1062020
The measurement of the fusion neutron yield provides a direct relationship with fusion power and is hence an important measure of experimental performance. In pulsed neutron emission scenarios, such as those experienced in dense plasma focus devices, inertial confinement fusion and even in short-pulse tokamak experiments, considerations of the dyna…
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UKAEA-CCFE-PR(20)1152020
Spectrum unfolding is a key tool used together with diagnostics in the determination of nuclear fields that are associated with a range of nuclear technologies spanning fusion, fission, nuclear medicine and accelerator domains. The underlying process requires a mathematical method for solving the Fredholm integral equation of the first kind. This p…
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UKAEA-CCFE-PR(20)692020
Molybdenum is a potential material for future nuclear fusion experiments and power plants. It has good thermo-mechanical properties and can be readily fabricated, making it attractive as an alternative material to tungsten (the current leading candidate) for high neutron flux and high thermal load regions of fusion devices. Unfortunately, exposu…
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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-CP(23)082019
Conventional means of fast neutron detection typically involves moderation and subsequent detection of thermal neutrons via gas filled detectors such as He-3, or alternatively indirect neutron detection via gamma activation systems. Whilst these are often the most conclusive systems for neutron detection, inherent timing and energy information asso…
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UKAEA-CCFE-CP(23)052019
For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design. A multi-step simulation process combining Monte Carlo Neutron Transport simulations with inventory simulations have been performed to estimate the activa…
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UKAEA-CCFE-PR(19)762019
Shutdown dose rate calculations provide an essential input to the design and research of fusion power plant technology. They allow the estimation of dose to personnel and equipment during planned and unplanned maintenance. The mesh coupled rigorous 2 step (MCR2S) methodology used at Culham Centre for Fusion Energy (CCFE) was originally developed to…
Showing 11 - 20 of 36 UKAEA Paper Results