欧洲DEMO HCPB育种毯原型模型的热-水力结垢

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Gaurav Verma, Guangming Zhou, Francisco A. Hernández
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引用次数: 0

摘要

氦冷却卵石床(HCPB)包层概念是欧洲聚变示范电厂(DEMO)驱动包层的主要候选方案,是在欧洲聚变框架的工作包育种包层(WPBB)中开发的。HCPB包层的一个关键组成部分是第一壁(FW),它必须承受来自等离子体的高热流,同时尽可能保持均匀的温度分布。这种均匀性是通过交替冷却剂流动设计实现的。目前的研究重点是第一面墙原型模型(FW-PMU)的热工水力缩放方法,以复制HCPB毯的热工和水力性能。FW-PMU旨在模拟HCPB繁殖毯(BB)第一壁的流动分布和热行为,包括从增殖区歧管到燃料增殖管脚的流动模式。在本工作中,采用功率体积缩放方法通过分析无量纲参数来保持特征时间比,而增殖区流形中组件尺寸的缩放确保了速度场的一致性。FW-PMU将在卡尔斯鲁厄理工学院的HELOKA高压高温氦设备中进行测试,以验证HCPB第一墙设计在实际操作条件下的可行性,推进其在聚变能源系统中的潜在部署。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Thermal-hydraulic scaling of the prototypical mock-up for European DEMO HCPB breeding blanket
The Helium-Cooled Pebble Bed (HCPB) blanket concept is a leading candidate for the driver blanket in the European Fusion Demonstration Power Plant (DEMO), developed within the EUROfusion framework's Work Package Breeding Blanket (WPBB). A crucial component of the HCPB blanket is the First Wall (FW), which must withstand high heat fluxes from the plasma while maintaining a uniform temperature distribution as much as possible. This uniformity is achieved through an alternating coolant flow design. The present study focuses on the thermal-hydraulic scaling methodology for the First Wall-Prototype Mock-Up (FW-PMU) to replicate the HCPB blanket's thermal and hydraulic performance. The FW-PMU is designed to emulate the flow distribution and thermal behavior of the HCPB Breeding Blanket (BB) First Wall, including flow patterns from the Breeder Zone Manifold to the fuel-breeder pins. In the present work, a power-to-volume scaling approach is employed to maintain the characteristic time ratio by analyzing non-dimensional parameters, while scaling of component dimensions in the breeder zone manifold ensures a consistent velocity field. The FW-PMU is set for testing in HELOKA, a high-pressure, high-temperature helium facility at the Karlsruhe Institute of Technology to validate the HCPB First Wall design under realistic operating conditions, advancing its potential deployment in fusion energy systems.
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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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