Elevating zero dimensional global scaling predictions to self-consistent theory-based simulations

Elevating zero dimensional global scaling predictions to self-consistent theory-based simulations
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将零维全局尺度预测提升为自洽的基于理论的模拟

DOI:
10.1063/5.0148886
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发表时间:
2023
期刊:
影响因子:
2.2
通讯作者:
J. Candy
J. Candy
中科院分区:
物理与天体物理3区
文献类型:
--
作者:
T. Slendebroek;J. Mcclenaghan;O. Meneghini;B. Lyons;Sterling P. Smith;T. Neiser;N. Shi;J. Candy

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我们在OMFIT集成建模框架内开发了一个创新的工作流程,稳定性,运输,平衡和基座(STEP)-零维(0 D)。通过对国际托卡马克物理活动全球H模约束数据库的系统验证,我们证明了STEP-0 D,平均而言,预测的能量约束时间的平均相对误差小于19%。此外,该工作流程在预测拟议的聚变反应堆的等离子体方面显示出了很大的潜力,例如经济实惠的,鲁棒的,紧凑的(ARC)反应堆,欧洲示范发电厂(EU-DEMO)和中国聚变工程试验堆(CFETR),表明H因子在0.9和1.2之间。STEP-0 D允许从0 D量开始对托卡马克方案进行基于理论的预测。工作流程从PRO-创建模块开始,使用与IPB 98(y,2)约束缩放相同的0 D量生成物理上一致的等离子体轮廓和平衡。这为STEP模块设置了起点,STEP模块进一步在基于理论的平衡、核心运输和基座物理模型之间迭代,以产生自洽的解决方案。鉴于这些属性,STEP-0 D不仅提高了预测等离子体性能的准确性,而且还提供了一条通往新型聚变发电厂设计工作流程的道路。当与优化中的工程和成本模型集成时,这种新方法可以消除不同保真度的等离子体模型之间的迭代协调。这种更有效的设计过程的潜力支持STEP-0 D对未来聚变发电厂发展的重大贡献。
We have developed an innovative workflow, Stability, Transport, Equilibrium, and Pedestal (STEP)-zero-dimensional (0D), within the OMFIT integrated modeling framework. Through systematic validation against the International Tokamak Physics Activity global H-mode confinement database, we demonstrated that STEP-0D, on average, predicts the energy confinement time with a mean relative error of less than 19%. Moreover, this workflow showed promising potential in predicting plasmas for proposed fusion reactors such as the affordable, robust, compact (ARC) reactor, the European demonstration power plant (EU-DEMO), and the China fusion engineering test reactor (CFETR) indicating moderate H-factors between 0.9 and 1.2. STEP-0D allows theory-based prediction of tokamak scenarios, beginning with 0D quantities. The workflow initiates with the PRO-create module, generating physically consistent plasma profiles and equilibrium using the same 0D quantities as the IPB98(y,2) confinement scaling. This sets the starting point for the STEP module, which further iterates between theory-based physics models of equilibrium, core transport, and pedestal to yield a self-consistent solution. Given these attributes, STEP-0D not only improves the accuracy of predicting plasma performance but also provides a path toward a novel fusion power plant design workflow. When integrated with engineering and costing models within an optimization, this new approach could eliminate the iterative reconciliation between plasma models of varying fidelity. This potential for a more efficient design process underpins STEP-0D's significant contribution to future fusion power plant development.
西南等离子体物理研究所(中国)
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