2011/08/19 by J. Ménard, L. Bromberg, T. Brown +19 · 4 citations
Physics and Astronomy · Materials Science · Engineering · #Magnetic confinement fusion research #Fusion materials and technologies #Superconducting Materials and Applications #Tokamak #Stellarator #Blanket #Nuclear engineering #Fusion power #Commercialization #Neutron transport #Spherical tokamak #Power station #Magnetic confinement fusion #Thermonuclear fusion #Nuclear physics #Computer science #Neutron #Physics #Materials science #Electrical engineering #Engineering #Plasma
paper · doi:10.1088/0029-5515/51/10/103014
openalex publication_date 2011/08/19 · openalex created_date 2025/10/10 · openalex updated_date 2026/07/11
A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e. a device ultimately capable of small net electricity production in as compact a facility as possible and in a configuration scalable to a full-size power plant. A key capability for a pilot-plant programme is the production of high neutron fluence enabling fusion nuclear science and technology (FNST) research. It is found that for physics and technology assumptions between those assumed for ITER and nth-of-a-kind fusion power plant, it is possible to provide FNST-relevant neutron wall loading in pilot devices. Thus, it may be possible to utilize a single facility to perform FNST research utilizing reactor-relevant plasma, blanket, coil and auxiliary systems and maintenance schemes while also targeting net electricity production. In this paper three configurations for a pilot plant are considered: the advanced tokamak, spherical tokamak and compact stellarator. A range of configuration issues is considered including: radial build and blanket design, magnet systems, maintenance schemes, tritium consumption and self-sufficiency, physics scenarios and a brief assessment of research needs for the configurations.