The ITER Neutral Beam Test Facility includes development, testing, and optimization of the full prototype of the ITER Heating Neutral Beam injectors (HNBs), named MITICA. A 40 MW precursor D⁻/H⁻ beam will be produced and then neutralised and filtered along the beamline, aiming to obtain 18 MW D⁰/H⁰ beam at the calorimeter and 16.5 MW during operation into the plasma. A gas neutraliser and an electrostatic residual ion dump will process the beam together with a calorimeter, necessary for commissioning and conditioning in HNBs, and for beam dumping in MITICA.

The three beamline components are formed by in-vacuum actively cooled panels made of seamless CuCrZr drilled bars and swirl tubes without armour directly exposed to beam particles. Heat fluxes up to 20 MW/m² will be exhausted through water-cooled channels operating up to 1 h in subcooled boiling. Critical heat flux and fully developed boiling were verified using semi-empirical correlations validated for divertor fingers and limiter plates. These correlations were implemented in 1D–3D customised codes simulating local nucleate boiling heat transfer conditions. Moreover, the panels were verified against creep-fatigue by simulating plastic strains under the expected cyclic thermal loads. During beam operation, the beamline components performance will be monitored using 700 embedded thermo-mechanical sensors for protection and for ITER HNBs requirement verification.

The design solutions were developed consistently with intermediate inspections during assembly to limit repairs, modification of compensation members for tolerance control in dimensional chains, remote handling operations, and nuclear radiation level at ITER. The design of coolant-vacuum barriers was adapted to implement corrosion, welding, and inspection requirements.

Prototypes implementing different manufacturing solutions were produced by three potential suppliers of MITICA beamline components. This strategy led to an early assessment of production reliability and cost-effective manufacturing techniques based on proven industrial expertise. Then, the supplier selected for the procurement of the beamline components will be supported with addressed performances during the follow up.

ITER中性束测试设施包括名为MITICA的ITER加热中性束喷射器（HNB）完整原型的开发，测试和优化。甲40 MW前体d ^- / H ^-光束将被生产，然后中和，沿射束线过滤，目的是获得18 MW d ⁰ / H ⁰在量热计光束和操作期间16.5兆瓦到等离子体中。气体中和器和静电残留离子收集器将与热量计一起处理离子束，这对于HNB中的调试和调理以及MITICA中的离子束收集是必需的。

这三个束线组件由真空内主动冷却的面板形成，该面板由无缝的CuCrZr钻杆和旋流管制成，而铠装则不会直接暴露于束状颗粒。热通量高达20 MW / m ²将通过在过冷沸腾状态下运行长达1小时的水冷通道排出。临界热通量和充分形成的沸腾通过使用偏心爪和限流板验证的半经验相关关系进行了验证。这些相关性是在1D–3D定制代码中实现的，这些代码模拟了局部核沸腾传热条件。此外，通过在预期的循环热负荷下模拟塑性应变，对面板进行了抗蠕变疲劳验证。在光束运行期间，将使用700个嵌入式热机械传感器监控光束线组件的性能，以提供保护和ITER HNB需求验证。

设计解决方案的开发与组装过程中的中间检查一致，以限制维修，修改补偿构件以进行尺寸链公差控制，远程处理操作以及ITER的核辐射水平。冷却液-真空屏障的设计适用于满足腐蚀，焊接和检查要求。

三家潜在的MITICA Beamline组件供应商生产了实施不同制造解决方案的原型。该策略导致基于成熟的行业专业知识对生产可靠性和具有成本效益的制造技术进行早期评估。然后，在后续行动中，为选定的光束线组件采购的供应商将获得解决的性能支持。