Million-kilowatt nuclear power plant shaft seal reactor coolant pump (Hua Pump No. 1) passed the appraisal

On Jan 10 2025, the China Machinery Industry Federation and the China General Machinery Industry Association organized a prototype appraisal meeting in Shenyang for the "Million-kilowatt Nuclear Power Plant Shaft Seal Reactor Coolant Pump (Hua Pump No. 1)" (Model: HLZB-100) jointly developed by China General Nuclear Power Engineering Co., Ltd. and Shenyang Blower Group Co., Ltd. The appraisal meeting was co-chaired by Huang Li, President of the China General Machinery Industry Association, and Sui Yongbin, former chief engineer of the China Machinery Industry Federation.

Academicians of the Chinese Academy of Engineering Ye Qizhen and Yu Junchong serve as the leader and deputy leader of the expert group of the appraisal committee respectively. The expert group is composed of experts from China National Nuclear Corporation, CGN, CGN Power, China Huadian, Hualong International, Shanghai Jiao Tong University, CGN Nuclear Power Operation, China Nuclear Power Institute, CGN Research Institute, Shandong Zhaoyuan Nuclear Power, Fujian Fuqing Nuclear Power and other units.

The experts and representatives attending the meeting listened to the research and development unit's summary report on the overall design, key technology research and prototype trial production of the reactor coolant pump, reviewed relevant documents and materials, and witnessed the disassembly of the reactor coolant pump components after the full-flow test.

After questioning and discussion, the expert group believes that the main innovations and technical features of the "Million-kilowatt Nuclear Power Plant Shaft Seal Reactor Coolant Pump (Hua Pump No. 1)" are: for the first time, a complete forward development system for shaft seal reactor coolant pump R&D design, component and whole machine manufacturing, and test verification has been established, and modularization, digitization, visualization and other technologies have been used to independently develop a four-bearing shaft seal reactor coolant pump; the reactor coolant pump fluid dynamic shaft seal and fluid static shaft seal have been independently developed, and a number of key technologies such as high-pressure large-diameter mechanical seal fluid-solid thermal coupling calculation, high-precision micron-level morphology processing and inspection, rubber material high temperature resistance, and accident condition hot performance test have been overcome; for the first time in China, a full-scale natural circulation capacity verification test of the emergency shaft seal injection system and a full-characteristic test of the gas-liquid two-phase of the hydraulic model were carried out, which provided a basis for the integrity of the system design under the condition of shaft seal losing injection water and the two-phase hydraulic characteristics for accident analysis; the key components surface modification treatment, water-lubricated graphite bearing mounting and hydraulic components precision manufacturing technologies have been developed to realize the digitalization, visualization and modular assembly of the whole machine.

The appraisal committee believes that the "million-kilowatt nuclear power plant shaft seal reactor coolant pump (Hua Pump No. 1)", which was developed for the first time using the forward development system, has completely independent intellectual property rights, has been granted 34 invention patents, has reached the international advanced level, has significant economic and social benefits and prospects for widespread promotion and application in nuclear power plants.