One-Dimensional Transport Code Modeling of the Divertor-Limiter Region in Tokamaks

J. M. Ogden; C. E. Singer; D. E. Post; R. V. Jensen; F. G.P. Seidl

doi:10.1109/TPS.1981.4317436

One-Dimensional Transport Code Modeling of the Divertor-Limiter Region in Tokamaks

J. M. Ogden, C. E. Singer, D. E. Post, R. V. Jensen, F. G.P. Seidl

Research output: Contribution to journal › Article › peer-review

Abstract

A model of the divertor-limiter scrapeoff region has been incorporated into the BALDUR one-dimensional tokamak transport code. Simulations of the proposed Toroidal Fusion Test Reactor (TFTR), and Poloidal Divertor (PDX) experiments and existing Alcator-A tokamak experiments have been carried out for ohmic and neutral beam heated cases. In particular, we have studied how the edge conditions and energy-loss mechanisms in PDX depend upon plasma density, and compared our results with analytic estimates. The sensitivity of the results to changes in the transport coefficients and scrapeoff model is discussed with particular reference to the power loading on the TFTR limiter.

Original language	English (US)
Pages (from-to)	274-282
Number of pages	9
Journal	IEEE Transactions on Plasma Science
Volume	9
Issue number	4
DOIs	https://doi.org/10.1109/TPS.1981.4317436
State	Published - Dec 1981
Externally published	Yes

ASJC Scopus subject areas

Nuclear and High Energy Physics
Condensed Matter Physics

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10.1109/TPS.1981.4317436

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abstract = "A model of the divertor-limiter scrapeoff region has been incorporated into the BALDUR one-dimensional tokamak transport code. Simulations of the proposed Toroidal Fusion Test Reactor (TFTR), and Poloidal Divertor (PDX) experiments and existing Alcator-A tokamak experiments have been carried out for ohmic and neutral beam heated cases. In particular, we have studied how the edge conditions and energy-loss mechanisms in PDX depend upon plasma density, and compared our results with analytic estimates. The sensitivity of the results to changes in the transport coefficients and scrapeoff model is discussed with particular reference to the power loading on the TFTR limiter.",

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AU - Post, D. E.

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AU - Seidl, F. G.P.

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AB - A model of the divertor-limiter scrapeoff region has been incorporated into the BALDUR one-dimensional tokamak transport code. Simulations of the proposed Toroidal Fusion Test Reactor (TFTR), and Poloidal Divertor (PDX) experiments and existing Alcator-A tokamak experiments have been carried out for ohmic and neutral beam heated cases. In particular, we have studied how the edge conditions and energy-loss mechanisms in PDX depend upon plasma density, and compared our results with analytic estimates. The sensitivity of the results to changes in the transport coefficients and scrapeoff model is discussed with particular reference to the power loading on the TFTR limiter.

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One-Dimensional Transport Code Modeling of the Divertor-Limiter Region in Tokamaks

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