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Учёные объяснили, как код SPIDER преобразует методы термоядерного синтеза.

Российские исследователи выполнили моделирование параметров вытянутой плазмы в токамаке с использованием кода SPIDER. Они смогли получить численную оценку вириальных отношений, которые описывают взаимосвязь равновесных характеристик тороидальной плазмы через интегральные величины, определяемые на основе данных внешних магнитных измерений. Ранее были получены аналитические оценки, и сейчас проводилась проверка их точности.
Учёные объяснили, как код SPIDER преобразует методы термоядерного синтеза.

The work has been published in the journal Physics of Plasmas. Nuclear fusion is one of the most promising technologies for generating clean and virtually inexhaustible energy. The plasma beta (βp) and internal inductance (ℓi) parameters are crucial for characterizing the operation of tokamaks and determining plasma equilibrium. The challenge of separating these parameters emerged over 60 years ago when V. D. Shafranov (corresponding member of the USSR Academy of Sciences since 1981, academic of the Russian Academy of Sciences since 1997) demonstrated in his works that their combination naturally arises in the integral consequences of the equilibrium equations. Since then, researchers have been striving to find effective methods for their separation, which is a significant task for plasma diagnostics and theory.

Scientists from MIPT, the M. V. Keldysh Institute of Applied Mathematics of the Russian Academy of Sciences, and the Kurchatov Institute conducted three series of plasma equilibrium calculations in a tokamak: at low, medium, and high pressure. Each series involved an elliptical cross-section with an elongation varying from K = 1 (circular plasma) to K = 2.4.

They employed numerical methods to calculate the integrals that define the right-hand sides of the standard virial relations for elongated plasma in tokamaks. The research utilized the SPIDER code, which allows modeling various plasma configurations with elliptical cross-sections. In each series of calculations, the dependencies of the integrals on plasma parameters, the elongation of magnetic surfaces, and radial derivatives of displacement and elongation were analyzed.

The results indicated that the deviation of the integrals from analytical estimates does not exceed 10 percent, confirming the accuracy of the proposed analytical expressions. Specifically, it was found that the integral S2 exhibits a weak dependence on elongation, which is an important finding for further research.

“Our study underscores the significance of considering parameters such as elongation and internal inductance for accurately describing plasma behavior in tokamaks. This opens up new possibilities for real-time plasma diagnostics and control,” said Vladimir Pustovito, a researcher at the MIPT Department of Plasma Energy.

The novelty of this research lies in providing numerical estimates for integrals for which compact analytical expressions were previously obtained.

The work of Russian scientists paves the way for new prospects in nuclear fusion research. In particular, it can be utilized to optimize the operation of tokamaks like ITER and to develop new plasma diagnostic methods. The application of the results obtained will enhance plasma control and improve the efficiency of nuclear reactors.

The findings of the study can be applied to optimize the operation of tokamaks, develop new precise methods for measuring plasma parameters, and deepen scientific understanding of plasma behavior under various conditions, potentially leading to new discoveries in the field of nuclear fusion.