A. Valentine T. Berry S. Bradnam H. Chohan T. Eade C. Grove J. Hagues K. Hearn J. Hodson K. Lennon J. Naish J. Neilson C. Nobs L. Packer A. Turner T. Turner L. Woodall R. Worrall
Global research programmes seeking to achieve a commercially viable model of a fusion power plant are being accelerated at an unprecedented rate. One critical element to the design and licensing is an accurate understanding of the radiation environment throughout the plant lifetime and subsequent decommissioning phase. The radiation field which res…
PreprintT. Eade S. Bradnam P. Kanth
A new method for the calculation of Shutdown Dose Rates (SDDR) has been developed, the Novel-1-Step (N1S) method. The new method retains the benefits of only requiring a single radiation transport calculation, as in the use of the direct-1-step (D1S) method, while removing the need for pre-calculations to determine dominant nuclides and time corr…
Preprint PurchaseG.W. Bailey M.R. Gilbert T.A. Berry T. Eade C. Bachmann U. Fischer
Previous studies of the European Demonstration fusion reactor concept (DEMO) have shown that the expected amounts of radioactive waste at end of life (EOL) are of the order of 104 tonnes. These studies also suggested that comparable amounts of waste will be classified as low level waste (LLW) and intermediate level waste (ILW) 100 yea…
PreprintA.Valentine N.Fonnesu B.Bienkowska E.Laszynska D.Flammini R.Villari G.Mariano T.Eade T.Berry L.Packer
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 PublishedT. A. Berry C. R. Nobs A. Dubas R. Worrall T. Eade J. Naish L. W. Packer
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 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 PublishedM.R. Gilbert T. Eade C. Bachmann U. Fischer N.P. Taylor
Waste-production predictions for the future demonstration fusion power plant (DEMO) are necessary to produce an accurate picture of the likely environmental and economic costs of radioactive waste disposal at end-of-life (EOL). Even during the conceptual stage of DEMO design it is important to perform waste assessment so as to avoid potential surpr…
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 PublishedM.R. Gilbert T. Eade C. Bachmann U. Fischer N.P. Taylor
Inventory calculations have a key role to play in designing future fusion power plants because, for a given irradiation field and material, they can predict the time evolution in chemical composition, activation, decay heat, gamma-dose, gas production, and even damage (dpa) dose. For conceptual designs of the European DEMO fusion reactor such calcu…
Preprint PublishedT. Eade S. Lilley Z. Ghani E. Delmas
The requirement for maintenance in areas with relatively high shutdown dose rate fields is a key issue to address in the design and engineering of ITER, next generation devices and future commercial fusion reactors. In order to estimate the shutdown dose rate during maintenance and intervention scenarios CCFEs Mesh Coupled implementation of the R…
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