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Nuclear power and safety in China
Published in David Toke, Geoffrey Chun-Fung Chen, Antony Froggatt, Richard Connolly, Nuclear Power in Stagnation, 2021
David Toke, Geoffrey Chun-Fung Chen, Antony Froggatt, Richard Connolly
However, unlike the CNNC, CGNPC was more inclined to purchase reactor technology directly from overseas at the beginning of its establishment. The reactor deployed in Daya Bay in 1994 was the M310 reactor Framatome, a French enterprise, had designed (NTI 2011; Forrest and Braun 2017, 33). This does not mean that CGNPC does not design. After the completion of the nuclear power project in Daya Bay, CGNPC created a domestically produced reactor design (model CPR-1000), which China’s preparatory electric field later used. The emergence of the technological innovation resulted from the introduction of and learning from overseas technology.
Transient Simulations of CPR1000 Nuclear Power Plant Implementing Advanced Mechanical Shim Control System
Published in Nuclear Science and Engineering, 2018
Shifa Wu, Jiashuang Wan, Hongbing Song, Xinyu Wei, Fuyu Zhao, Shripad Revankar
The improved Chinese Pressurized Water Reactor (CPR1000), built and operated by China General Nuclear Power Group, is one of the main reactor types in China.1 It employs the Mode-G (Ref. 2) control method for reactor power control, using G-banks and R-banks to obtain fast and accurate reactor power control, respectively. The Mode-G control strategy could provide satisfactory control performance when the fraction of nuclear power is small and the reactor is generally base loaded. However, this obsolete control system has poor performance on load-follow maneuvers. It requires manually changing the soluble boron concentration to compensate the reactivity (known as chemical shim) during load-follow maneuvers, which is not only not automated but also time consuming. Moreover, this operation will produce large quantities of effluent, and it will become extremely difficult to change the boron concentration at the end of cycle due to the very low boron concentration.3 Therefore, the Mode-G control of CPR1000 is facing a great challenge when load-follow capability is becoming increasingly necessary in China.
A CNN-LSTM–Based Model to Fault Diagnosis for CPR1000
Published in Nuclear Technology, 2023
Changan Ren, He Li, Jichong Lei, Jie Liu, Wei Li, Kekun Gao, Guocai Huang, Xiaohua Yang, Tao Yu
In this study, a PWR three-loop–type NPP, specifically a CPR1000, was utilized. This power plant offers over ten distinct starting conditions to reproduce the plant’s initial operating characteristics at different operational points. PCTRAN software includes 20 operational failures commonly found in NPPs, including loss of flow, loss of alternating-current power, anticipated transient without trip, loss-of-coolant accident, and steam generator tube rupture, as well as certain extreme design issues. Furthermore, PCTRAN adheres to the “30-minute non-intervention” rule in emergency mode, the same as a real power plant.[13]