为加快实施创新驱动发展战略，持续推进核电领域关键核心技术攻关，近日，中国机械工业联合会和中国通用机械工业协会组织召开“AP/CAP 1000压水堆核电站大规模供热用再热调节阀”产品样机鉴定会，国核电力院牵头承担的“AP/CAP 1000压水堆核电站大规模供热条件下常规岛再热调节阀国产化研究”课题的研究成果顺利通过产品鉴定。鉴定委员会认为：研制的AP/CAP 1000压水堆核电站大规模供热用再热调节阀产品样机具有自主知识产权，填补了国内空白，主要性能指标达到国际同类产品先进水平，可在核电站推广应用。

本课题受山东核电有限公司委托，由国核电力院核能分公司牵头，与哈尔滨汽轮机厂有限责任公司基于合作研发、知识产权共有、收益共享、风险共担的原则，共同开展研发工作。该产品的研制成功，有力提升了我国对此类再热调节阀及其核心附件的自主化生产能力，消除了汽轮机关键设备对核能供热规模化发展的制约，充分展现了国核电力院在大型先进压水堆核电站常规岛热力系统关键设备方面的研发实力和技术水平。

In order to accelerate the implementation of the innovation-driven development strategy and continue to promote the key core technology research in the field of nuclear power, China Machinery Industry Federation and China General Machinery Industry Association recently organized the "AP/CAP 1000 Pressurized water reactor nuclear power plant large-scale heating reheat regulator valve" product prototype identification meeting. The research results of the project "Localization of conventional Island Reheat regulating valve under large-scale heating conditions of AP/CAP 1000 pressurized water reactor nuclear Power Plant" led by the National Nuclear Power Institute successfully passed the product eva luation. The appraisal committee believes that the AP/CAP 1000 pressurized water reactor nuclear power plant large-scale heating reheat regulating valve product prototype has independent intellectual property rights, fills the domestic gap, the main performance indicators reach the international advanced level of similar products, and can be promoted and applied in nuclear power plants.

This project is commissioned by Shandong Nuclear Power Co., LTD., led by the Nuclear Energy Branch of the State Nuclear Power Institute, and Harbin Turbine Works Co., LTD., based on the principles of cooperative research and development, intellectual property ownership, income sharing and risk sharing. The success of the development of this product has effectively improved China's autonomous production capacity of such reheat regulator and its core accessories, eliminated the constraints of key turbine equipment on the large-scale development of nuclear energy heating, and fully demonstrated the research and development strength and technical level of the National Nuclear Power Institute in the key equipment of the conventional island heat system of large advanced pressurized water reactor nuclear power plant.