“PROCESS“：聚变发电厂的系统代码.第2部分：工程
"PROCESS": a systems code for fusion power plants - Part 2:Engineering
摘要：
PROCESS是一个反应堆系统代码-它使用反应堆系统所有部分的简单模型来评估一个假设的核聚变电站的工程和经济可行性。PROCESS允许用户选择施加哪些约束，忽略哪些约束，因此在评估结果时，研究所使用的约束列表至关重要。合作者提交的新算法可以被纳入-例如安全性，第一壁侵蚀和疲劳寿命将是至关重要的，但尚未考虑在内。本文介绍了有关工厂的工程方面的算法。环向场（TF）线圈和中心螺线管被假定为默认情况下，由具有与ITER导体相同的属性的超导体缠绕而成。在失超期间的绕组温度和感应电压提供了对TF线圈中的电流密度的限制。上限被放置在TF线圈的结构材料的应力，使用一个简单的两层模型的内侧腿的线圈。电厂的热效率可以使用最大冷却剂温度来估计，并且容量因子来自计划内和计划外停机时间的估计，以及如果反应堆是脉冲的，则来自占空比。给出了一个脉冲发电厂的例子。
英文摘要：
PROCESS is a reactor systems code - it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New algorithms submitted by collaborators can be incorporated - for example safety, first wall erosion, and fatigue life will be crucial and are not yet taken into account. This paper describes algorithms relating to the engineering aspects of the plant. The toroidal field (TF) coils and the central solenoid are assumed by default to be wound from niobium-tin superconductor with the same properties as the ITER conductors. The winding temperature and induced voltage during a quench provide a limit on the current density in the TF coils. Upper limits are placed on the stresses in the structural materials of the TF coil, using a simple two-layer model of the inboard leg of the coil. The thermal efficiency of the plant can be estimated using the maximum coolant temperature, and the capacity factor is derived from estimates of the planned and unplanned downtime, and the duty cycle if the reactor is pulsed. An example of a pulsed power plant is given.
机构、总结、中文摘要均由AI分析而来，可能存在错误，请以论文正文为准。
