TRT divertor optimization in SOLPS-ITER modeling

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Дәйексөз келтіру

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Аннотация

The analysis of possible divertor working regimes and edge plasma parameters for TRT tokamak project is performed basing on modeling. It is shown that for the separatrix power of 18 MW corresponding to approximately twice higher full input power the low divertor integral heat flux 5 MW/m2 can be provided for the separatrix plasma density lower than 7 × 1019 m–3 and the effective charge Zeff lower than 2. These parameters are realistic for this device. In case of bigger separatrix power the working regime is possible with higher divertor heat load still within the technological limits of the machine. Modeling also shows positive effect of the increase of the distance between the separatrix and the vacuum vessel structures and better performance of the corner divertor configuration comparing to the “ITER-like” one.

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Авторлар туралы

P. Molchanov

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

P. Kudrevatykh

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

N. Shtyrkhunov

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

E. Kaveeva

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Хат алмасуға жауапты Автор.
Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

V. Rozhansky

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

I. Senichenkov

Peter the Great St. Petersburg Polytechnic University; Institution “Project Center ITER”

Email: E.Kaveeva@spbstu.ru
Ресей, St. Petersburg, 195251; Moscow, 123182

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