K.V. Ellis H. Lux E. Fable R. Kembleton M. Siccinio
Systems codes are used in the conceptual phases of fusion reactors design. They employ a multitude of simplified models to simulate an entire power plant and ensure that designs are self-consistent, viable and optimised with respect to a given figure of merit. Their strength is the fast determination of an overall design. However, their output shou…
Preprint PublishedLei Tang Kun Yan Biao Cai Yiqiang Wang Bin Liud Saurabh Kabrae Moataz M Attallaha Yong Liu
Deformation mechanisms of high entropy alloys (HEAs) at cryogenic temperatures have attracted extensive research interest. We used in situ neutron diffraction to study the tensile behavior of a face-centered-cubic HEA at 77 and 15 K and compared its stacking fault energy (SFE) at ambient and cryogenic temperatures. The SFE dropped from 28…
Preprint PublishedD. Patel M.D. Richardson B. Jim S. Akhmadaliev R. Goodall A.S. Gandy
A novel multicomponent alloy, V2.5Cr1.2WMoCo0.04, produced from elements expected to favour a BCC crystal structure, and to be suitable for high temperature environments, was fabricated by arc melting and found to exhibit a multiphase dendritic microstructure with W-rich dendrites and V-Cr segregated to the inter-de…
Preprint PublishedM. Coleman S. McIntosh
As part of our aim to develop a reactor design framework, we present here our solution for the optimisation of plasma equilibria and tokamak poloidal field systems. A 2-D, free boundary, ideal magneto-hydrodynamic plasma equilibrium solver is described. We use it within the BLUEPRINT reactor design framework to design the plasma equilibria and po…
Preprint PublishedPaul James Barron Alexander W Carruthers Jonathan W Fellowes Nick G Jones Huw Dawson Ed J Pickering
By mixing elements with favourable nuclear activation properties to create high-entropy alloys, it may be possible to create a material that can withstand a nuclear fusion environment while minimising the radioactive waste produced. Such a material could be used in the extreme thermal and irradiation conditions of a fusion blanket. A suite of previ…
Preprint PublishedZ. Vizvary M. L. Richiusa C. Bachmann C. Vorpahl
The DEMO blanket attachment concept is challenging due to several factors: the harsh radiation environment, the thermal expansion, the electro-magnetic loads, the remote maintenance feasibility, and the accurate control of the alignment of the breeding blanket first wall during operation. There are two inboard and three outboard blanket segments…
Preprint PublishedY. Q. Wang S. J. Clark B. Cai D. Alba Venero K. Yan M. Gorley E. Surrey D. G. McCartney S. Sridhar P. D. Lee
Ti-containing micro-alloyed steels are often alloyed with molybdenum (Mo) to gain superior ageing-resistance through reduced nano-precipitate coarsening, although the exact mechanism is still disputed. Using small angle neutron scattering (SANS), we characterize precipitate composition and coarsening in Ti micro-alloyed steels with and without M…
Preprint PublishedA.C. Field L.N. Carter N.J.E. Adkins M.M. Attallah M.J. Gorley M. Strangwood
Two high purity tungsten powders, produced via different manufacturing techniques, were characterized to determine size distribution, morphology, thermal properties and flow characteristics and thus, the likely suitability for Laser Powder Bed Fusion (LPBF) production. Specimens from duplicate builds were produced with the two powders and character…
Preprint PublishedKuo Zhang Ermile Gaganidze Michael Gorley
This report covers the initial progress on the development of material property handbook (MPH) of baseline CuCrZr, within the Materials Engineering Data and Design Integration (MAT-EDDI) of EUROfusion Material Database and Handbook group. Initial drafting of the baseline CuCrZr MPH structure is presented, with inclusion of available data, figure…
Preprint PublishedMike Fursdon Jeong-ha You Muyuan Li
Guidelines are presented for the recommended method of assessing by analysis the structural integrity of divertor plasma facing components (PFCs) under high heat flux (HHF) loads. The objective is to enable analysis to provide greater supporting evidence for PFC qualification (which for ITER is currently achieved by test alone) and to provide reaso…
Preprint Published