球形托卡马克电站过程设计与SARAS的标杆设计

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Christopher Ashe , P.N. Maya , Stuart I. Muldrew , Shishir Deshpande
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引用次数: 0

摘要

系统代码中的不确定性可以基于所使用模型中的假设以及优化前输入参数的组合来分析。在本文中,我们在一系列球形托卡马克设计中比较了PROCESS和SARAS代码,这些设计已被确定为印度- demo计划上可能的试点工厂和商业设计。总体而言,两种规范的计算结果部分相似,但由于边缘安全系数的计算和处理不同,导致其他关键参数的计算差异约为±20%。主要用等离子体电流、β分量和随后的约束时间计算。Bootstrap电流分数计算被证明是不可靠的,并且超出了未来电厂的管理范围,这突出了对更接近电厂条件的新替代模型的需求。利用基于蒙特卡罗的不确定性量化,重点研究了内环场线圈腿的认知不确定性,我们发现两种规范在应力量化方面有合理的一致性。悲观的不确定性假设仍然显示了在降低环形场强的情况下性能恢复的空间。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Benchmarking of spherical tokamak power plant design in PROCESS and SARAS
Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of ±20%. Mainly with plasma current, β components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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