G. Caruso(a) S. Ciattaglia(b) B. Colling(c) L. Di Pace(d) D.N. Dongiovanni(e) M. D’Onorio(a) M. Garcia(f) X. Z. Jin(g) J. Johnston(c) D. Leichtle(g) T. Pinna(e) M. T. Porfiri(e) W. Raskob(g) N. Taylor(c) N. Terranova(e) R Vale(c) all contributors to the WPSAE
The Safety and Environmental Work Package (WPSAE) has the scope to progress the safety studies for the future EU DEMO reactor, in the frame of the Eurofusion programme. A Generic Site Safety Report (GSSR) has been designed to include all the steps necessary to cover the safety issues of the nuclear fusion plant, from the definition of principles an…
Preprint PublishedJ. Keep T. Berry S. Budden B. Chuilon B. Colling E. Flynn S. Ha C. Jackson G. Keech W. Leong G. Mathew E. Organ C. Shaw A. Wilde
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 PublishedC.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 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 PublishedA. Valentine B. Colling R. Worrall J. Leppänen
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…
Preprint PublishedTim Eade Bethany Colling Jonathan Naish Lee Packer Alex Valentine
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 PublishedA. Turner A. Burns B. Colling J. Leppänen
Nuclear analysis supporting the design and licensing of ITER is traditionally performed using MCNP and the reference model ‘C-Model’, however the complexity of C-Model has resulted in the geometry creation and integration process becoming increasingly time-consuming. Serpent 2 is still a beta code, however recent enhancements mean that it could…
Preprint PublishedB. R. Colling T. Eade M. R. Gilbert J. Naish S. Zheng
Computational models created for neutronics assessment through solid geometry conversion are often specific to the analysis being performed. The use of unstructured mesh geometry has the potential to reduce the build time of MCNP models, reduce inaccuracies introduced through flux averaging over different components and material mixing, and make us…
Preprint PublishedL. W. Packer P. Batistoni S. Bradnam B. C. Colling S. Conroy Z. Ghania M. R. Gilbert S. Jednorog E. Laszyńska D. Leichtle I. Lengar J.W.Mietelski R. Misiak C.R.Nobs M. Pillon S. Popovichev V. Radulović I.E. Stamatelatos T. Vasilopoulou A. Wójcik-Gargula JET Contributors
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 PublishedJ.E. Menard T. Brown L. El-Guebaly M. Boyer J. Canik B. Colling R. Raman Y. Zhai P. Buxton B. Covele C. D'Angelo A. Davis S. Gerhardt M. Gryaznevich M. Harb T.C. Hender S. Kaye D. Kingham M. Kotschenreuther S. Mahajan R. Maingi E. Marriott E.T. Meier L. Mynsberge C. Neumeyer M. Ono S.A. Sabbagh V. Soukhanovskii P. Valanju R. Woolley
A Fusion Nuclear Science Facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The spherical torus/tokamak (ST) is a leading candidate for an FNSF due to its potentially high neutron wall loading and modular configuration. A key consid…
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