CHIMERA Fusion Technology Facility: Testing and Virtual Qualification
CHIMERA Fusion Technology Facility: Testing and Virtual Qualification
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CHIMERA 融合技术设施：测试和虚拟资格认证
DOI：
10.1080/15361055.2022.2147766
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发表时间：
2023
影响因子：
0.9
通讯作者：
Barrett T
中科院分区：
文献类型：
--
作者：
Barrett T
加热和磁研究联合装置聚变技术试验设施正在建造之中。该设施将能够在真空高热通量、静态和脉冲磁场以及高温/高压水冷却的组合条件下，对聚变材料和组件模块进行半整体测试，测试尺寸可达ITER测试包层模块箱。本文报告了CHIMERA基线设计的高级能力和计划的测试程序，并介绍了使用模拟进行虚拟测试、鉴定和现场监测。组件模型测试的第一步是从现场采集数据，建立几何和其他测量，并将其传输到一个集成的计算模型，可以密切模仿物理资产，并形成一个数字器手机监听器该数字复制品不仅可以在设施中进行物理测试之前进行查询，从而优化测试程序，而且与后续测试数据相结合，它还可以提供比单独使用测试数据更深入的实验结果。数字复制品被用作数字孪生的基础，数字孪生与运行中的实验实时耦合，并且正在开发中，作为聚变反应堆监视的一个关键方面。用于测试的物理模型可以在强水平磁场内的整个表面上经受高达0.5 MW/m2的真空热通量。中心场可达4 T，测试区域的峰值为5 T。相同的组件实体模型也可以经受斜坡率为12 T/s的重复磁场脉冲，这可以模拟等离子体破裂的负载条件。目前正在进行设施升级，以便包括一个液态金属循环回路，从而能够研究磁流体动力学效应，并增加一个高热通量系统，该系统使用一个非常高功率的连续波激光器，以便在一个小型模型区域内实现20兆瓦/平方米的偏滤器相关热通量。给出了四个例子来说明目前预见的物理测试程序。
The Combined Heating and Magnetic Research Apparatus (CHIMERA) fusion technology test facility is under construction. The facility will be uniquely capable of semi-integral testing of fusion materials and component modules up to the size of the ITER test blanket module box, under combined conditions of in-vacuum high heat flux, static and pulsed magnetic fields, and high-temperature/high-pressure water cooling. This paper reports the high-level capabilities of the CHIMERA baselined design and the planned program of testing and describes the proposed strategy for use of simulations for virtual testing, qualification, and in-situ monitoring.The first step in testing of a component mock-up is to take data from as-built geometry and other measurements and transmit them to an integrated computational model that can closely mimic the physical asset and form a digital replica. Not only can this digital replica be queried in advance of physical testing in the facility, allowing optimization of the test program, but combined with subsequent test data, it also can deliver much greater insight into experimental results than can be obtained using test data alone. The digital replica is used as the basis for a digital twin, which is live coupled to the running experiment, and is under development as a proposed key facet of fusion reactor surveillance in-service. Physical mock-ups for testing can be subjected to in-vacuum heat flux up to 0.5 MW/m2over the entire surface while within a strong horizontal magnetic field. The central field can be up to 4 T with a peak in the test region of 5 T. The same component mock-ups can also be subjected to repeated magnetic field pulses with ramp rate 12 T/s, which can simulate loading conditions of a plasma disruption. Facility upgrades are underway to include a liquid metal circulation loop to allow the study of magnetohydrodynamics effects and to add a high-heat-flux system using a very high-power continuous-wave laser to achieve divertor-relevant heat fluxes of 20 MW/m2over the area of a small-scale mock-up. Four examples are given to illustrate the physical testing program that is currently foreseen.
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