Implementation and verification of a HELIAS module for the systems code PROCESS

F. Warmer; C.D. Beidler; A. Dinklage; K. Egorov; Y. Feng; J. Geiger; R. Kemp; P. Knight; F. Schauer; Y. Turkin; D. Ward; R. Wolf; P. Xanthopoulos

doi:10.1016/j.fusengdes.2014.12.021

Implementation and verification of a HELIAS module for the systems code PROCESS

F. Warmer
, C.D. Beidler
, A. Dinklage
, K. Egorov
, Y. Feng
, J. Geiger
, R. Kemp
, P. Knight
, F. Schauer
, Y. Turkin
, D. Ward
, R. Wolf
, P. Xanthopoulos

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

9 Citations (Scopus)

Abstract

In order to study design points of next-step fusion devices such as DEMO, comprehensive systems codes are commonly employed. The code package PROCESS is such a tool, widely used for tokamak systems studies. In this work, the implementation and verification of a HELIAS module into PROCESS is addressed. These HELIAS models include: a plasma geometry model based on Fourier coefficients, a basic island divertor model, as well as a coil model which combines scaling aspects based on the Helias 5-B reactor design in combination with analytic inductance and field calculations. The models are verified firstly with respect to W7-X. Secondly, the generality of the models is used to represent the tokamak which is compared against the original tokamak PROCESS models using a DEMO design as reference case. Both approaches show very good agreement.

Original language	English
Pages (from-to)	2227-2230
Number of pages	4
Journal	Fusion Engineering and Design
Volume	98-99
DOIs	https://doi.org/10.1016/j.fusengdes.2014.12.021
Publication status	Published - Oct 2015
Externally published	Yes

Funding

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the European Union's Horizon 2020 research and innovation programme under grant agreement number 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Keywords

HELIAS
PROCESS
Systems code
Verification

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10.1016/j.fusengdes.2014.12.021

Cite this

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title = "Implementation and verification of a HELIAS module for the systems code PROCESS",

abstract = "In order to study design points of next-step fusion devices such as DEMO, comprehensive systems codes are commonly employed. The code package PROCESS is such a tool, widely used for tokamak systems studies. In this work, the implementation and verification of a HELIAS module into PROCESS is addressed. These HELIAS models include: a plasma geometry model based on Fourier coefficients, a basic island divertor model, as well as a coil model which combines scaling aspects based on the Helias 5-B reactor design in combination with analytic inductance and field calculations. The models are verified firstly with respect to W7-X. Secondly, the generality of the models is used to represent the tokamak which is compared against the original tokamak PROCESS models using a DEMO design as reference case. Both approaches show very good agreement.",

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doi = "10.1016/j.fusengdes.2014.12.021",

language = "English",

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journal = "Fusion Engineering and Design",

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AU - Warmer, F.

AU - Beidler, C.D.

AU - Dinklage, A.

AU - Egorov, K.

AU - Feng, Y.

AU - Geiger, J.

AU - Kemp, R.

AU - Knight, P.

AU - Schauer, F.

AU - Turkin, Y.

AU - Ward, D.

AU - Wolf, R.

AU - Xanthopoulos, P.

PY - 2015/10

Y1 - 2015/10

N2 - In order to study design points of next-step fusion devices such as DEMO, comprehensive systems codes are commonly employed. The code package PROCESS is such a tool, widely used for tokamak systems studies. In this work, the implementation and verification of a HELIAS module into PROCESS is addressed. These HELIAS models include: a plasma geometry model based on Fourier coefficients, a basic island divertor model, as well as a coil model which combines scaling aspects based on the Helias 5-B reactor design in combination with analytic inductance and field calculations. The models are verified firstly with respect to W7-X. Secondly, the generality of the models is used to represent the tokamak which is compared against the original tokamak PROCESS models using a DEMO design as reference case. Both approaches show very good agreement.

AB - In order to study design points of next-step fusion devices such as DEMO, comprehensive systems codes are commonly employed. The code package PROCESS is such a tool, widely used for tokamak systems studies. In this work, the implementation and verification of a HELIAS module into PROCESS is addressed. These HELIAS models include: a plasma geometry model based on Fourier coefficients, a basic island divertor model, as well as a coil model which combines scaling aspects based on the Helias 5-B reactor design in combination with analytic inductance and field calculations. The models are verified firstly with respect to W7-X. Secondly, the generality of the models is used to represent the tokamak which is compared against the original tokamak PROCESS models using a DEMO design as reference case. Both approaches show very good agreement.

KW - HELIAS

KW - PROCESS

KW - Systems code

KW - Verification

UR - https://www.scopus.com/pages/publications/84942834188

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DO - 10.1016/j.fusengdes.2014.12.021

M3 - Article

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VL - 98-99

SP - 2227

EP - 2230

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Implementation and verification of a HELIAS module for the systems code PROCESS

Abstract

Funding

Keywords

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