Abstract

New superconductor types and performance levels are being developed and have enabled consideration of higher-field, smaller-size devices. In this paper, sizing options for the next Fusion Energy System Study (FESS) design study are explored. The 2016/2017 baseline Fusion Nuclear Science Facility (FNSF) used a bucked and wedged solution with a large external case mainly to support out-of-plane loads and allow radial servicing. Use of a larger case to provide inner leg compression may be needed for the higher-field, smaller devices. These structural concepts have been employed in FIRE, IGNITOR, and C-Mod. Each of these concepts will be investigated as candidates for a next machine study. Recommendations will be made as to how these concepts can be incorporated into systems codes.

The iterative design of the poloidal field coil system and the iterative choice of scenario currents are needed to go along with toroidal field (TF) coil support concepts. Concepts that employ a bucked solution require assessment of cancellation of the central solenoid radially outward and the TF radially inward load, and thus affect the sizing of both. Ideally better but simple structural models of the poloidal coils can be built into the scenario development codes to address advanced TF support schemes. Simplified spreadsheet assessments of structural concepts are presented, and these are benchmarked against finite element analyses. Possible options for the FNSF and next machine studies are assessed in terms of achievable fields and space allocation.

摘要

新的超导体类型和性能水平正在开发中，并且可以考虑更高场、更小尺寸的设备。在本文中，探讨了下一次聚变能源系统研究 (FESS) 设计研究的大小选择。2016/2017 基准核聚变核科学设施 (FNSF) 使用带大型外壳的弯曲楔形解决方案，主要用于支持平面外载荷并允许径向维修。对于场强更高、尺寸更小的设备，可能需要使用更大的外壳来提供内腿压缩。这些结构概念已用于 FIRE、IGNITOR 和 C-Mod。这些概念中的每一个都将作为下一个机器研究的候选对象进行研究。将就如何将这些概念纳入系统代码提出建议。

极向场线圈系统的迭代设计和场景电流的迭代选择需要与环形场 (TF) 线圈支持概念相一致。采用反向解决方案的概念需要评估取消中央螺线管径向向外和 TF 径向向内负载，从而影响两者的尺寸。理想情况下，可以将极向线圈的更好但简单的结构模型内置到场景开发代码中，以解决高级 TF 支持方案。介绍了结构概念的简化电子表格评估，并以有限元分析为基准。FNSF 和下一个机器研究的可能选项根据可实现的领域和空间分配进行评估。