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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…
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UKAEA-CCFE-PR(19)512019
Only limited data exist on the effect of neutron irradiation on the brittle to ductile transition (BDT) in tungsten. This work investigates the increase in brittle to ductile transition temperature (BDTT) following neutron irradiation to 1.67 displacements per atom, using four-point bend tests over a range of temperatures (623 – 1173 K) and strai…
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UKAEA-CCFE-PR(18)792018
This paper reports new activities conducted as part of the JET technology programme under the WP-JET3 ACT sub-project collaboration. The aim of the sub-project is to take advantage of the significant 14 MeV neutron fluence expected during JET operations to irradiate samples of materials that will used in the manufacturing of main ITER tokamak compo…
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UKAEA-CCFE-PR(18)12018
This paper details progress in experimental characterisation work at JET for the long-term irradiation station conducted as part of a project to perform activation experiments using ITER materials. The aim is to take advantage of the significant 14 MeV neutron yield expected during JET operations to irradiate samples of materials that will be used …
Showing 11 - 20 of 33 UKAEA Paper Results