T. 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 PurchaseJ. Peng H Zhang Y. Wang M. Richardson X. Liu D. Knowles M. Mostafavi
The small punch test (SPT) has been widely used to evaluate the mechanical properties of materials for the nuclear industry due to its advantage of requiring minimal sample volumes. In this paper, the correlation between SPT and uniaxial tensile testing (UTT) is investigated for three materials used in the plasma-facing components of fusion reactor…
Preprint PublishedD.J.M. King A.J. Knowles D. Bowden M.R. Wenman S. Capp M. Gorley J. Shimwell L. Packer M.R. Gilbert A. Harte
This Review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered …
Preprint PublishedAndrej Horvat Mike Fursdon Nicolas Mantel Rob Bamber Martin Webb Davide Kleiner Roberta Santori
An important contribution to the mechanical stresses present in the ITER ICH antenna is related to the non-uniform heating of its front section due to RF losses, plasma and charge exchange, and the effects of neutron radiation. As a consequence, intensive convective cooling is necessary to maintain temperature and the related thermally induced s…
PreprintNeill Taylor Sergio Ciattaglia Dave Coombs Xue Zhou Jin Jane Johnston Karine Liger Guido Mazzini Juan Carlos Mora Tonio Pinna Maria Teresa Porfiri Egidijus Urbanovicius
Pre-conceptual design studies for a European Demonstration Fusion Power Plant (DEMO) have been in progress since 2014. At this stage, while a range of design options are being considered, it is essential that assessments are carried out of the safety and environmental impact of these options. This is not only to ensure that the DEMO plant is op…
PublishedJ. Lion F. Warmer H. Wang C.D. Beidler S.I. Muldrew R. C. Wolf
We present modifications of the systems code Process that allow for a description of a general class of stellarator power plants, based on a stellarator coil-set and the respective MHD plasma equilibrium. For this, we modify Process such that each stellarator confi…
Preprint PublishedG. 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 PublishedA.Valentine R. Worrall
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 PublishedTriestino Minniti Heather Lewtas
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 PublishedI. Kodeli E. Sartori
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