H Meyer the STEP Team
The programme to design plasma scenarios for the Spherical Tokamak for Energy Production (STEP), a reactor concept aiming at net electricity production, seeks to exploit the inherent advantages of the spherical tokamak (ST) while making conservative assumptions about plasma performance. This approach is motivated by the large gap between present-da…
PreprintNousheen Nawal Hanni Lux Member IEEE Rhian Chapman James R. Cowan Member APM
Being a novel technology, estimating costs for fusion power plants comes with large uncertainties. Cost uncertainties in prototypes arise from various sources and reduce with programme maturity (including the selection of a site), technical and design maturity, maturity of the commercial strategy (e.g., make vs. buy decisions, partnering de…
PreprintA. J. Leide E. Hintsala M. Davies D. Goddard D. Liu
Coated nuclear fuel particles, most commonly tri-structural isotropic (TRISO), are intended for use in advanced high temperature reactors. The coatings of these particles are designed to protect and encapsulate the fuel during all stages of the fuel cycle, from manufacturing, through operation and up to disposal. It is vital to understand the me…
PublishedYao Ren Robert Skilton
Piping systems that transport coolant and breeding fluid are naturally an essential part of the support system of the nuclear fusion power plants. Following a campaign of operations, the reactor is required to be shut down and maintained entirely. Pipes connected to the reactor components are to be cut, re-welded or re-joined, and inspected non-des…
PreprintV.G. Kiptily P.J. Bonofiglo T. Craciunescu J. Eriksson M. Fitzgerald V. Goloborodko M. Nocente S. Menmuir M. Podestà M. Poradzinski D. Rigamonti Z. Stancar S.E. Sharapov H. Sun D.M. Taylor M. Tardocchi P. Beaumont F. Belli F.E. Cecil C.D. Challis R. Coelho M. Curuia R. Dumont J. Garcia M. Garcia-Munoz Z. Ghani Ye. Kazakov D. Keeling E. Lerche C.F. Maggi J. Mailloux P. Mantica M.J. Mantsinen D. Marocco C. Perez von Thun F. Rimini
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Charged fusion products of this reaction, α-particles (4He-ions), are born with an average energy of 3.5 MeV. Transferring energy to the thermal plasma during their slowing down, the…
PreprintL. Reali M.R. Gilbert M. Boleininger S.L. Dudarev
Neutrons interacting with atomic nuclei in most of the materials included in the current fusion reactor designs—notably tungsten, ferritic and stainless steels, copper alloys—generate a γ-photon flux that is comparable in magnitude and e…
Preprint PublishedD. Batty L. Manes A. West M. Patel I. Caliskanelli P. Paoletti
In the nuclear industry, the need for improved reliability in current and future technology hinders the deployment of autonomous robotic systems. The following research aims to develop a method of reliably mapping a large environment and abstracting the map into a sparse node graph to create a more efficient data form. The proposed data form all…
PurchaseAlice Cryer Alfie Sargent Fumiaki Abe Paul Dominick Baniqued Ipek Caliskanelli Hasan Kivrak Hanlin Niu Salvador Pacheco-Gutierrez Alexandros Plianos Masaki Sakamoto Tomoki Sakaue Wataru Sato Shu Shirai Yoshimasa Sugawara Harun Tugal Andika Yudha Robert Skilton
The maturation of Virtual Reality software introduces new avenues of nuclear decommissioning research. Digital Mockups are an emerging technology which provide a virtual representation of the environment, objects or processes, supporting the whole lifecycle of product development and operations. This paper provides a survey on currently available s…
PreprintM. Anderton C. Baus T. P. Davis R. Pearson K. Mukai J. Pollard K. Taylor S. Kirk J. Hagues
Tritium self-sufficiency is one of the fundamental challenges for deuterium-tritium nuclear fusion reactors. The combination of key high temperature radiation shielding materials that possess dense, high neutron absorption cross-section, and moderation properties, and tritium breeding materials could involve interesting design spaces for the centra…
PreprintG. Qin H. Wu C. Li A. Ji S. Budden
The hybrid kinematic mechanism (HKM) as a remote handling subsystem of Demonstration Fusion Power Plant (DEMO) breeding blanket (BB) is undergoing extensive theoretical analysis and feasibility verification. In this paper, the forward and inverse kinematic models of HKM are respectively developed by combining the Newtonian iterative method and the …
Published