Searching the Plasma Geometry and Configuration Spaces for Feasible Tokamak Design Point

Ehab Hassan; C. E. Kessel; J. M. Park; P. B. Snyder; C. S. Collins

doi:10.13182/T128-42154

Searching the Plasma Geometry and Configuration Spaces for Feasible Tokamak Design Point

Ehab Hassan, C. E. Kessel, J. M. Park, P. B. Snyder, C. S. Collins

Research output: Contribution to journal › Conference article › peer-review

Abstract

A workflow starts with zero-dimensional (0D) systems code to scan a large data set of nuclear engineering and physics parameters followed by studying the pedestal structure and the influence of various schemes of heating and current drives on the fusion power is presented in this paper. The design point achieved in this study fulfills most of the nuclear engineering and fusion plasma requirements such as high fusion power with net electric power above 20 MW, ideal MHD stable plasma (β_N > β_N,limit), a minimum safety factor (q_min) greater than ^m/n=³/2, and acceptable divertor heating load and average neutron wall load. The use of the IPS-FASTRAN framework provides improved calculations for the H/CD efficiency and better prediction for the confinement factor (H₉₈) using TGLF transport code, the difference between the 0D systems code and 1.5D higher fidelity codes could be attributed to the density peaking assumption which will be explored to optimize the fusion performance. In addition, the plasma current used in these scenarios will be optimized to realize scenarios of non-inductive operations with large bootstrap current fractions.

Original language	English
Pages (from-to)	148-150
Number of pages	3
Journal	Transactions of the American Nuclear Society
Volume	128
DOIs	https://doi.org/10.13182/T128-42154
State	Published - 2023
Event	2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023 - Indianapolis, United States Duration: Jun 11 2023 → Jun 14 2023

Funding

1NOTICE OF COPYRIGHT: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This work was supported by the US Department of Energy, Office of Science, Basic Energy Sciences Program under contract numbers DE-AC05-00OR22725 and DE-SC0017992

Funders	Funder number
Basic Energy Sciences Program	DE-AC05-00OR22725, DE-SC0017992
U.S. Department of Energy
Office of Science

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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title = "Searching the Plasma Geometry and Configuration Spaces for Feasible Tokamak Design Point",

abstract = "A workflow starts with zero-dimensional (0D) systems code to scan a large data set of nuclear engineering and physics parameters followed by studying the pedestal structure and the influence of various schemes of heating and current drives on the fusion power is presented in this paper. The design point achieved in this study fulfills most of the nuclear engineering and fusion plasma requirements such as high fusion power with net electric power above 20 MW, ideal MHD stable plasma (βN > βN,limit), a minimum safety factor (qmin) greater than m/n=3/2, and acceptable divertor heating load and average neutron wall load. The use of the IPS-FASTRAN framework provides improved calculations for the H/CD efficiency and better prediction for the confinement factor (H98) using TGLF transport code, the difference between the 0D systems code and 1.5D higher fidelity codes could be attributed to the density peaking assumption which will be explored to optimize the fusion performance. In addition, the plasma current used in these scenarios will be optimized to realize scenarios of non-inductive operations with large bootstrap current fractions.",

author = "Ehab Hassan and Kessel, {C. E.} and Park, {J. M.} and Snyder, {P. B.} and Collins, {C. S.}",

note = "Publisher Copyright: {\textcopyright} 2023 American Nuclear Society. All rights reserved.; 2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023 ; Conference date: 11-06-2023 Through 14-06-2023",

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AU - Hassan, Ehab

AU - Kessel, C. E.

AU - Park, J. M.

AU - Snyder, P. B.

AU - Collins, C. S.

PY - 2023

Y1 - 2023

N2 - A workflow starts with zero-dimensional (0D) systems code to scan a large data set of nuclear engineering and physics parameters followed by studying the pedestal structure and the influence of various schemes of heating and current drives on the fusion power is presented in this paper. The design point achieved in this study fulfills most of the nuclear engineering and fusion plasma requirements such as high fusion power with net electric power above 20 MW, ideal MHD stable plasma (βN > βN,limit), a minimum safety factor (qmin) greater than m/n=3/2, and acceptable divertor heating load and average neutron wall load. The use of the IPS-FASTRAN framework provides improved calculations for the H/CD efficiency and better prediction for the confinement factor (H98) using TGLF transport code, the difference between the 0D systems code and 1.5D higher fidelity codes could be attributed to the density peaking assumption which will be explored to optimize the fusion performance. In addition, the plasma current used in these scenarios will be optimized to realize scenarios of non-inductive operations with large bootstrap current fractions.

AB - A workflow starts with zero-dimensional (0D) systems code to scan a large data set of nuclear engineering and physics parameters followed by studying the pedestal structure and the influence of various schemes of heating and current drives on the fusion power is presented in this paper. The design point achieved in this study fulfills most of the nuclear engineering and fusion plasma requirements such as high fusion power with net electric power above 20 MW, ideal MHD stable plasma (βN > βN,limit), a minimum safety factor (qmin) greater than m/n=3/2, and acceptable divertor heating load and average neutron wall load. The use of the IPS-FASTRAN framework provides improved calculations for the H/CD efficiency and better prediction for the confinement factor (H98) using TGLF transport code, the difference between the 0D systems code and 1.5D higher fidelity codes could be attributed to the density peaking assumption which will be explored to optimize the fusion performance. In addition, the plasma current used in these scenarios will be optimized to realize scenarios of non-inductive operations with large bootstrap current fractions.

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JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023

Y2 - 11 June 2023 through 14 June 2023

ER -

Searching the Plasma Geometry and Configuration Spaces for Feasible Tokamak Design Point

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UN SDGs

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