Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

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

Physics Design and Economic Assessment of a Long-Pulsed Fusion Power Plant

16 Oct 2014, 08:30
4h
Green 8-9 (Hotel Park Inn Pribaltiyskaya)

Green 8-9

Hotel Park Inn Pribaltiyskaya

Saint Petersburg, Russian Federation
Poster Poster 5

Speaker

Mr Dehong Chen (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences)

Description

A fusion power plant based on long-pulsed operated tokamak fusion reactor was proposed to avoid the issues of steady-state operation of non-inductive current driven methods. The plasma current, excepting the bootstrap current, is only driven inductively to sustain several hours. The burning stage can be sustained by α heating and started by ohmic and radio frequency wave heating methods. Thus, the axillary heating methods was cut in order to save about 1/3 of gross electric power supply to them. With 0.8 of plant capability assumed, the capital cost and cost of electricity (COE) were assessed and minimized to search feasible physics designs with stable power balance and under feasible engineering conditions. The plasma equilibrium and charge evolution were analyzed with TSC (Tokamak Simulation Code) to verify the magnetic flux requirement and stability of self-sustained heating and inductive current driven. The COE was also compared with the case of steady-state operation with sensitivity analysis of duty ratio and efficiency of non-inductive current driven methods. The results indicated that the feasibility of the periodic operated fusion reactor depends on its duty ratio and can be an alternative scenario for future demonstration reactor and fusion power plant.
Country or International Organisation China
Paper Number SEE/P5-15

Primary author

Mr Dehong Chen (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences)

Co-authors

Dr Jieqiong Jiang (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences) Dr Wenxue Duan (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences) Dr Yawei Hou (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences) Prof. Yican Wu (Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences)

Presentation materials