L. W. Packer P. Batistoni B. Colling K. Drozdowicz M. Fabbri Z. Ghani M. R Gilbert S. Jednorog E. Laszynska D. Leichtlef J.W.Mietelski C.R. Nobs M. Pillon I.E. Stamatelatos T. Vasilopoulou R. Villari A. Wójcik-Gargula JET Contributors
The planned high-profile experiments during 2020 at the Joint European Torus (JET), notably including a deuterium-tritium (DT) experimental phase, are expected to produce large neutron yields, in the region of 1021 neutrons. The scientific objectives are linked with a technology programme, WPJET3, to deliver the maximum scientific and…
PreprintJ.A.Bromley R.Vale M.R.GIlbert
The paper looks at a selective smelting regime where higher activity components are smelted with lower activity components with the aim to reduce the amount of ILW waste for disposal. This has been applied to the European DEMO Fusion Plant HCPB 2015 baseline design waste assessment. The paper assesses the structural steels in the breeder blanket…
PreprintC.R. Nobs L. W. Packer P. Batistoni B. Colling Z. Ghani M. Gilbert S. Loreti K. Mergia S. Mesoloras I. Michelakaki M. Pillon M. I. Savva I. E. Stamatelatos K. Triantou T. Vasilopoulou
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…
Preprint PublishedL. W. Packer S. Allan S. B. Bradnam M. R. Gilbert T. Stainer
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…
Preprint PublishedR. Worrall B. Colling M. R. Gilbert E. Litherland-Smith C. R. Nobs L. W. Packer C. Wilson A. Zohar
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 PublishedP.D. Edmondson B. Gault M.R. Gilbert
Tungsten is the prime candidate material for the plasma facing divertor system and first wall armor of future nuclear fusion reactors. However, the understanding of the microstructural and chemical evolution of pure tungsten under neutron irradiation is relatively unknown, in part due to a lack of experimental data on this topic. Here, single cr…
Preprint PublishedAndrey Litnovsky Janina Schmitza Felix Klein Karen De Lannoyea Sophie Weckauf Arkadi Kreter Marcin Rasinski Jan W. Coenen Christian Linsmeier Jesus Gonzalez-Julian Martin Bram Ivan Povstugar Thomas Morgan Duc Nguyen-Manh Mark Gilbert Damjan Sobieraj Jan S. Wróbel
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first wall cladding may exceed 1000oC and remain for months leading to tungsten oxidation. The radioactive tungsten oxide can be mobilized to the environment at rates of 10 – 150 kg per hour. Smart tungsten-based alloys are under develop…
Preprint PublishedM.R. Gilbert L.W. Packer T. Stainer
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 PublishedL W Packer M Angeloni M R Gilbert M Pillon J-C Sublet
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…
Preprint PublishedOlga Vilkhivskaya Mark Gilbert
Recent studies of the neutron irradiation conditions predicted in the plasma-exposed first wall of a conceptual design of fusion DEMO power plant implementing the SPECTRA-PKA code have shown the importance of taking into consideration per-channel analysis of the high-energy threshold reactions for an accurate evaluation of their contribution to …
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