dorsal/arxiv
View SchemaCalculations of Energy Losses due to Atomic Processes in Tokamaks with Applications to the ITER Divertor
| Authors | D. Post, J. Abdallah, R. E. H. Clark, N. Putvinskaya |
|---|---|
| Categories | |
| ArXiv ID | plasm-ph/9506004 |
| URL | https://arxiv.org/abs/plasm-ph/9506004 |
| DOI | 10.1063/1.871257 |
Abstract
Reduction of the peak heat loads on the plasma facing components is essential for the success of the next generation of high fusion power tokamaks such as the International Thermonuclear Experimental Reactor (ITER) 1 . Many present concepts for accomplishing this involve the use of atomic processes to transfer the heat from the plasma to the main chamber and divertor chamber walls and much of the experimental and theoretical physics research in the fusion program is directed toward this issue. The results of these experiments and calculations are the result of a complex interplay of many processes. In order to identify the key features of these experiments and calculations and the relative role of the primary atomic processes, simple quasi-analytic models and the latest atomic physics rate coefficients and cross sections have been used to assess the relative roles of central radiation losses through bremsstrahlung, impurity radiation losses from the plasma edge, charge exchange and hydrogen radiation losses from the scrape-off layer and divertor plasma and impurity radiation losses from the divertor plasma. This anaysis indicates that bremsstrahlung from the plasma center and impurity radiation from the plasma edge and divertor plasma can each play a significant role in reducing the power to the divertor plates, and identifies many of the factors which determine the relative role of each process. For instance, for radiation losses in the divertor to be large enough to radiate the power in the divertor for high power experiments, a neutral fraction of 10-3 to 10-2 and an impurity recycling rate of netrecycle of ~ 10^16 s m^-3 will be required in the divertor.
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"abstract": "Reduction of the peak heat loads on the plasma facing components is essential\nfor the success of the next generation of high fusion power tokamaks such as\nthe International Thermonuclear Experimental Reactor (ITER) 1 . Many present\nconcepts for accomplishing this involve the use of atomic processes to transfer\nthe heat from the plasma to the main chamber and divertor chamber walls and\nmuch of the experimental and theoretical physics research in the fusion program\nis directed toward this issue. The results of these experiments and\ncalculations are the result of a complex interplay of many processes. In order\nto identify the key features of these experiments and calculations and the\nrelative role of the primary atomic processes, simple quasi-analytic models and\nthe latest atomic physics rate coefficients and cross sections have been used\nto assess the relative roles of central radiation losses through\nbremsstrahlung, impurity radiation losses from the plasma edge, charge exchange\nand hydrogen radiation losses from the scrape-off layer and divertor plasma and\nimpurity radiation losses from the divertor plasma. This anaysis indicates that\nbremsstrahlung from the plasma center and impurity radiation from the plasma\nedge and divertor plasma can each play a significant role in reducing the power\nto the divertor plates, and identifies many of the factors which determine the\nrelative role of each process. For instance, for radiation losses in the\ndivertor to be large enough to radiate the power in the divertor for high power\nexperiments, a neutral fraction of 10-3 to 10-2 and an impurity recycling rate\nof netrecycle of ~ 10^16 s m^-3 will be required in the divertor.",
"arxiv_id": "plasm-ph/9506004",
"authors": [
"D. Post",
"J. Abdallah",
"R. E. H. Clark",
"N. Putvinskaya"
],
"categories": [
"plasm-ph",
"physics.plasm-ph"
],
"doi": "10.1063/1.871257",
"title": "Calculations of Energy Losses due to Atomic Processes in Tokamaks with Applications to the ITER Divertor",
"url": "https://arxiv.org/abs/plasm-ph/9506004"
},
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