UKAEA Papers

Showing 11 - 20 of 90 UKAEA Paper Results
2021
UKAEA-CCFE-PR(21)55

Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powerful simulation code for nuclear systems analysis. Originally developed for reactor physics applications, the scope of the code now extends to coupled multi-physics simulations and radiation transport. The latter has allowed adoption of the code by t…

Preprint
2021
UKAEA-CCFE-PR(21)40

The ability to detect undesired volumetric defects in reactor components could affect the safety and reliability of a fusion power plant and change the expected lifetime and performance of the reactor. This is even more true for critical reactor parts like plasma-facing components which have to withstand challenging in-vessel conditions due to a co…

Preprint
2021
UKAEA-CCFE-PR(21)28

The creation of an international shielding benchmark database was presented in 1988 at the International Reactor Shielding Conference (ICRS7) in Bournemouth, UK. M. Salvatores was among the authors of the proposal and had promoted and contributed to the project since the first initiatives, showed continued interest and encouraged the devel…

Preprint Published
2021
UKAEA-CCFE-PR(21)18

During operation fusion reactor components will be exposed to long periods of neutron irradiation. As such, a reactor's structural steels will become activated and need to be disposed of as radioactive waste. Previous studies have shown that such wastes can struggle to meet low level waste requirements meaning that costly geological disposal may be…

Preprint Published
2020
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 c…

Preprint Published
2021
UKAEA-CCFE-CP(21)04

The use of small specimen test techniques (SSTT) to determine mechanical properties of irradiated materials has been studied over the previous decades both in fission and fusion programs, but also to characterise and optimise new materials by nuclear and non-nuclear communities. Currently a number of activities are running that focus on the standar…

Preprint
2020
UKAEA-CCFE-CP(21)01

DEMO is a key part of the EU fusion roadmap, and the programme reaches the end of the pre-conceptual phase with a gate review in 2020. As part of the work to complete this phase, eight Key Design Integration Issues (KDII’s) have been identified as critical to the programme. Two of these KDII’s identified a requirement for a more detailed archit…

Preprint Purchase
The published version of this paper is currently under embargo and will be available on 26/02/2023
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 consistently. Plant availability and lifetime will approach that of a…

Preprint Published
2021
UKAEA-CCFE-PR(21)12

Small punch creep (SPC) testing represents an effective way to rapidly assess the creep performance of novel materials and potentially monitor degradation of in-service components. Recent progress in standardisation has also led to improvements in data analysis. However, estimation of equivalent uniaxial stresses is still somewhat challenging and h…

Preprint Published
2021
UKAEA-CCFE-PR(21)10

The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime…

Preprint Published