UKAEA Journals

Showing 1 - 10 of 21 Journals Results
2021
UKAEA-CCFE-PR(21)17

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 comb…

Preprint
2021
UKAEA-CCFE-PR(21)14

As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300MW to 500 MW) safely and consistentl…

Preprint
2020
UKAEA-CCFE-PR(20)115

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…

Preprint Purchase
The published version of this paper is currently under embargo and will be available on 19/10/2022
2020
UKAEA-CCFE-PR(20)69

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…

Preprint Published
2019
UKAEA-CCFE-PR(19)76

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…

Preprint Published
2019
UKAEA-CCFE-PR(19)51

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…

Preprint Published
2018
UKAEA-CCFE-PR(18)79

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…

Preprint Published
2018
UKAEA-CCFE-PR(18)1

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 …

Preprint Published
2016
CCFE-PR(16)01

Tritium production is of critical importance to prospective DT fusion power plants. Lithium ceramic and beryllium based solid-type breeder blankets are an option for supplying the tritium required to sustain the DT plasma. This research investigates the time-varying tritium production in solid breeder blankets with different compositions. The breed…

Preprint Published
2015
CCFE-PR(17)24

Extensive neutronics and 3-D activation simulations were carried out to assess the levels of radiation throughout the ITER tokamak complex. The simulated radiation sources included D–T fusion neutrons exiting the cryostat and gamma rays arising from the activation of cooling water, activated pipe chases and cask transfers. Resultant biological dos…

Preprint Published