Albert D. Smith Jack M. Donoghue Alistair J.W. Garner David Lunt Allan Harte Keith Wilford Philip J. Withers Michael Preuss
Proton irradiation is often used as a proxy for neutron irradiation but the irradiated layer is typically
Preprint PublishedMichael Gorley Eberhard Diegele Ermile Gaganidze Ferenc Gillemot Gerald Pintsuk
The development of a specific materials database and handbook, for engineering design of in-vessel components of EU-DEMO, is an essential requirement for assessing the structural integrity by design. For key in-vessel materials, including EURFOER97, CuCrZr, Tungsten and dielectric and optical materials, this development has been ongoing now within …
Preprint PublishedStuart I. Muldrew Hanni Lux Tim C. Hender Bhavin Patel Peter J. Knight Garry M. Voss Howard R. Wilson
Spherical Tokamaks offer a number of potential advantages for a future fusion power plant. They have a high ratio of thermal to magnetic field pressure (beta) and strong flows, either of which could result in reduced turbulence. Fewer Toroidal Field (TF) coils and a different geometry offers the potential for new methods of remote maintenance …
Preprint PublishedA.J. Pearce R. Kembleton M. Kovari H. Lux J. Morris M. Siccinio
As conceptual design options for a demonstration fusion power plant (DEMO) are explored it is important to understand the design space for possible non-ITER like design options. The power exhaust is a key design driver for a fusion power plant, and puts strong constraints on the size of the machine. One candidate for a alternative design is a doubl…
Preprint PublishedA. Gray A. Davis E. Patelli
Nuclear data is at the heart of all nuclear science and technology. It represents the interaction probabilities of neutrons with matter and is used to construct distributions in particle transport Monte Carlo codes. Due to the difficulty and cost of conducting experiments, experimental reaction data is usually sparse or not present for the majority…
Preprint PublishedLee Aucott Hongbiao Dong Wajira Mirihanage Robert Atwood Anton Kidess Shian Gao Shuwen Wen John Marsden Shuo Feng Mingming Tong Thomas Connolley Michael Drakopoulos Chris R. Kleijn Ian M. Richardson David J. Browne Ragnvald H. Mathiesen Helen. V. Atkinson
Internal flow behaviour during melt-pool-based metal manufacturing remains unclear and hinders progression to process optimisation. In this contribution, we present direct time-resolved imaging of melt pool flow dynamics from a high-energy synchrotron radiation experiment. We track internal flow streams during arc welding of steel and measure insta…
Preprint PublishedS. I. Muldrew H. Lux V. Menon R. Srinivasan
Systems codes assess the viability of fusion reactor designs by using simplified models for the entire reactor system that allow for the exploration of large areas of parameter space. However, every design will have an associated uncertainty that arises from the accuracy of the models used, the assumptions made and the values of input parameters ad…
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 PublishedK.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 Published