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Oct 13 – 18, 2014
Hotel Park Inn Pribaltiyskaya
Europe/Moscow timezone

Diagnostics and Control for Steady State and Pulsed Tokamak DEMO

Oct 17, 2014, 8:30 AM
4h
Green 8-9 (Hotel Park Inn Pribaltiyskaya)

Green 8-9

Hotel Park Inn Pribaltiyskaya

Saint Petersburg, Russian Federation
Poster Poster 7

Speaker

Dr Francesco Paolo Orsitto (Associazione EURATOM-ENEA unita' tecnica fusione)

Description

This paper reports work done for EFDA PPPT in 2013. It includes the constraints of neutron fluence and Tritium Breeding Ratio(TBR) on diagnostics installation; the technology readiness level of a minimum diagnostics set for control (including burn control);an extended set of diagnostics for control code training; results on diagnostics technology; burn and divertor control. Two DEMO devices (2GW power) are considered:a long pulse inductive device (PLS) based on H-mode and a steady state(SS) fully non-inductive device. The differences in parameters and operational constraints lead to different requirements for the diagnosis and control of the devices. The space available is limited by cost constraints regarding blanket thickness and Li6 enrichment to achieve the necessary TBR>1, so in DEMO only 3-5m2 can be available. The DEMO neutron wall loading on the first wall (FW) is 1.82MW/m2 corresponding to 20dpa ( displacement per atom) in 2FPY (Full Power Year), ~7 times the ITER damage level on FW. The damage due to neutrons is maximum on the outboard equatorial side, and at a distance of 50cm from the first wall (FW) is 0.5dpa in 1FPY for DEMO1, while the damage decreases to 5x10-3dpa in 1FPY at 100cm from First Wall. Calculations are performed for EUROFER. As consequence, using tungsten recrystalized mirrors (resistant to 3dpa damage) is possible. So Microwave and IR(infrared) diagnostics are feasible on DEMO as well as direct line-of-sight techniques like neutronics and X-rays. These findings open up the possibility of polarimetry for plasma density and current control since Steady-state DEMO needs additional control on current and pressure profiles. Both devices( PLS and SS) need burn control at high electron temperature and the MHD control on neoclassical tearing modes. The divertor control must be considered implying the measurements of radiated power fraction, plasma temperature, density and composition. The extrapolation from ITER to DEMO is large but several promising techniques have been identified despite the nuclear and erosion-deposition problems.
Paper Number FIP/P7-8
Country or International Organisation Italy

Primary author

Dr Francesco Paolo Orsitto (Associazione EURATOM-ENEA unita' tecnica fusione)

Co-authors

Mr Antonio Silva (4Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal) Mr Claudius Morlock (Eurofusion Project Management Unit , Boltzmannstr. 2, 85748 Garching (Ge)) Dr Fabio Moro (ENEA Unita Tecnica Fusione Frascati(Italy)) Dr Gianfranco Federici (Eurofusion Project Management Unit , Boltzmannstr. 2, 85748 Garching (Ge)) Prof. Giuseppe Gorini (Istituto di Fisica del Plasma CNR, Via Roberto Cozzi, 53,20125 Milano (Italy)) Mr Ian Jenkins (CCFE Culham(UK)) Mr Ivan Duran (Institute of Plasma Physics AS CR, Za Slovankou 3, 182 00 Praha 8, Czech Republic) Mr Jachek Rzadkiewicz (National Centre for Nuclear Research, 05-400 Otwock, Poland) Dr Marco Tardocchi (Istituto di Fisica del Plasma CNR, Via Roberto Cozzi, 53,20125 Milano (Italy)) Mr Marek Scholz (Henryk Niewodniczański Institute of Nuclear Physics, PAN, Kraków, Poland) Mr Robert Felton (CCFE Culham(UK)) Dr Rosaria Villari (ENEA Unita Tecnica Fusione Frascati(Italy)) Mr Stiven Lilley (CCFE Culham(UK)) Dr Tom Todd (CCFE Culham (UK)) Dr Wolfgang Biel (Institute for Energy and Climate Research , FZ Julich)

Presentation materials