BEGIN:VCALENDAR VERSION:2.0 CALSCALE:GREGORIAN PRODID:UW-Madison-Physics-Events BEGIN:VEVENT SEQUENCE:0 UID:UW-Physics-Event-6121 DTSTART:20200928T170000Z DURATION:PT1H0M0S DTSTAMP:20260415T005645Z LAST-MODIFIED:20200921T151816Z LOCATION:Zoom Meeting SUMMARY:in present experiments \, Plasma Physics (Physics/ECE/NE 922) Seminar\, Dr. Alberto Loarte\, Head of Science Division of the ITER Or ganization DESCRIPTION:The ITER project aims to demonstrate the scientific and te chnological feasibility of fusion power for peaceful purposes and to g ain the knowledge necessary for the design of next stage fusion reacto rs. The project is organized as an international research and developm ent project with seven Members\; the European Union (represented by EU RATOM)\, Japan\, the People’s Republic of China\, India\, the Republ ic of Korea\, the Russian Federation and the USA. The overall aim of t he ITER project is reflected in its three fusion power production goal s (Q ≥ 10 gain for 300-500 s\, Q ≥ 5 for 1000s and Q ≥ 5 for 300 0s corresponding to steady-state tokamak operation) and associated fus ion technology demonstration.
\nTo define the plan of research a nd development and of the exploitation of the facility necessary to me et the ITER mission goals\, the ITER Research Plan (IRP) has been elab orated. The IRP is divided into two main phases after First Plasma dem onstration: operation in H/He plasmas (Pre-Fusion Plasma Operation (PF PO)) and in DD/DT plasmas (Fusion Plasma Operation (FPO)). These two m ain phases are subdivided into experimental campaigns\, separated by f urther assembly phases\, in which the tokamak ancillary systems (heati ng and current drive\, fuelling\, etc.) are progressively implemented to their baseline configurations to be completed before FPO (“Staged Approach”). The IRP describes the objectives of each operational ca mpaign consistent with the available tokamak systems\, details the exp erimental plan to achieve them (including options)\, and identifies th e main risks of the experimental plan to achieve the objectives of eac h phase and corresponding mitigation actions.
\nThe main physics o bjectives of the two initial experimental campaigns (PFPO-1 and PFPO-2 ) are the achievement of high confinement plasmas (H-mode) and the dem onstration of plasma operation up to the ITER design values for plasma current (15 MA) and toroidal field (5.3T) in L-mode plasmas. These ex periments will characterize for the first time energy and particle con finement in a tokamak plasma at the reactor scale\, to compare with th e extrapolations made on the basis of present experiments that have be en used for the ITER design. The FPO campaigns cover a long operationa l period from the start of DD plasma operation\, with the principal ob jectives being the demonstration of the Q = 10 inductive operation and Q = 5 operation with in-principle steady-state conditions. The exper imental plan to proceed from DD towards DT plasmas builds on the resul ts expected to be achieved in PFPO. It includes a verification of the L-mode 15 MA development path demonstrated in PFPO and the initial exp ansion of the H-mode operational space in DD plasmas from low values o f current and toroidal field. This is followed by a gradual evolution toward DT plasmas with increasing T content plasmas leading to a demo nstration of Q = 10 operation for a duration of 50 s. This initial pha se is then followed by experimental campaigns focused on increasing th e burn length of the inductive Q = 10 scenario towards the objective o f 300-500s and the development of the in-principle steady-state Q = 5 scenarios\, where the optimization of the pressure and plasma current profiles will be a main focus of the experimental programme.
\nThe presentation will introduce the ITER project\, describe progress in t he construction of the ITER tokamak device and its ancillary systems a nd will describe the experimental and modelling R&D required to suppor t the refinement or consolidation of the IRP in advance of its executi on in ITER itself.
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