4月24日 Key validation needs of EU-DEMO HCPB Breeding Blanket and its mockup BLUME in IFMIF-DONES

报告题目：Key validation needs of EU-DEMO HCPB Breeding Blanket and its mockup BLUME in IFMIF-DONES

报告人：Guangming Zhou

报告时间：2025年4月24日 下午14：00

报告地点：聚变堆园区202会议室

主持人：刘松林

报告人简介：

Dr. Guangming Zhou is a Permanent Research Scientist at the Karlsruhe Institute of Technology (KIT) in Germany, specializing in nuclear fusion technology. With over a decade of expertise, his work focuses on the design and engineering of tritium breeding blanket (TBB) systems—a key component in deuterium-tritium (D-T) fusion reactors for sustainable electricity generation. Dr. Zhou earned his Ph.D. from the University of Science and Technology of China in November 2016 and has been with KIT since January 2017. Since January 2021, he has served as the Lead Engineer and Coordinator for the Helium Cooled Pebble Bed (HCPB) Breeding Blanket program under the EUROfusion DEMO Breeding Blanket Project (WPBB). In this capacity, he leads a multidisciplinary team of 25+ full-time professionals, driving the strategic design, R&D, and implementation of the HCPB system. He oversees a multi-million-euro annual budget and coordinates collaboration among 10+ European research institutions, ensuring progress toward EUROfusion’s mission of developing commercially viable fusion energy.

报告摘要：

The tritium breeding blanket is an essential system in any deuterium-tritium (D-T) fusion electricity-producing device. Its primary functions include producing tritium to ensure fuel self-sufficiency, extracting high-grade heat for electricity generation, and shielding sensitive components from nuclear irradiation. Despite its critical role, the technical readiness level of tritium breeding blankets remains low. This talk will first provide an overview of the design of the Helium-Cooled Pebble Bed (HCPB) breeding blanket for the European DEMO fusion reactor. It will then emphasize the urgent need to improve the technical readiness level of tritium breeding blankets for fusion reactors. The IFMIF-DONES facility offers a unique opportunity to test tritium blanket technologies, given its large test volume and high neutron flux. In response to the need for testing blanket technology, a Blanket Functional Materials Module (BLUME) for the HCPB breeding blanket has been proposed. Preliminary designs of BLUME will be presented, followed by a discussion of future activities aimed at refining and consolidating the design.