中国ITER氦冷固态增殖剂实验包层系统设计研发进展

Development Progress of Chinese Helium Cooled Ceramic Breeder Test Blanket System

产氚包层是未来聚变堆实现氚燃料自持和发电的关键部件,为了验证氚增殖包层技术,中国与国际热氦聚变实验堆(ITER)国际组织签署了氦冷陶瓷增殖剂(HCCB)实验包层模块(TBM)协议,为聚变堆环境下的氚增殖包层技术测试提供了契机。通过与ITER国际组织的深入合作,中国已经完成中国氦冷固态增殖剂实验包层及其辅助系统(合称HCCBTBS)的概念设计并获得ITER国际组织批准,正在开展初步设计阶段的设计优化、材料与工艺研发和实验平台搭建,以进一步验证其设计合理性和可行性,这将为HCCBTBS在ITER实验堆上开展测试和氚增殖包层技术的发展奠定坚实基础。

Tritium breeding blanket is one of the key components for the future fusion reactor to realize the tritium fuel self-sufficiency and power generation.In order to validate the technology of tritium breeding blanket,China has signed the helium cooled ceramic breeder(HCCB)test blanket module(TBM)agreement with ITER organization,which provides the chance to test the TBB technologies under fusion reactor environment.Based on the deep cooperation with ITER Organization,China has completed the conceptual design of HCCB TBM and its ancillary systems(totally HCCB TBS),and obtained the approval by ITER Organization.The design optimization,R&D of materials and fabrication processes,construction of test facilities for preliminary design phase are under implementation now in order to further improve and verify the reasonability and feasibility of the design,which will provide the strong support for the testing of HCCB TBS in ITER and technology development of tritium breeding blanket.