China General Nuclear Power Group , formerly China Guangdong Nuclear Power Group , is a major clean energy corporation under the SASAC of the State Council.CGN has operating nuclear plants at Daya Bay Nuclear Power Plant, Ling Ao Nuclear Power Plant, Hongyanhe Nuclear Power Plant and Ningde Nuclear Power Plant, with five new nuclear power stations under construction and another 2 planned.CGN operates in other emerging energy industries like wind energy and solar energy, as well as more traditional industries like hydroelectricity. As of 2014 CGN operates power generation plant of the capacity: nuclear 8.3 GW, wind 4.7 GW, hydro 4.0 GW and solar 600 MW. Wikipedia.
Li S.,University of Science and Technology Beijing |
Wang Y.,University of Science and Technology Beijing |
Zhang H.,University of Science and Technology Beijing |
Xue F.,China General Nuclear Power Group |
Wang X.,University of Science and Technology Beijing
Materials and Design | Year: 2013
The cast austenite stainless steels were investigate in order to understand the microstructural evolution and mechanical properties in the long-term thermal aging at 400. °C for up to 20,000. h. Spinodal decomposition and G-phase precipitation in ferrite after long-term thermal aging lead to the degradation of mechanical properties. Ferrite hardness increases with aging time, but the austenite hardness does not change. Tensile strength is not strongly affected by aging time, but the plasticity has a significant decrease after long-term aging. Under impact with high strain rate, the ferrite phases deform by the way of deformation twinning. High stress concentration on the phase boundaries cause the phase boundary separating and the austenite's tearing off. © 2013 Elsevier Ltd.
He Q.,China General Nuclear Power Group |
Hasegawa Y.,University of Tokyo |
Kasagi N.,University of Tokyo
International Journal of Heat and Fluid Flow | Year: 2010
Numerical simulation of gas-liquid slug flow and associated heat transfer without phase change in a micro tube is carried out. The presence of a gas bubble causes recirculating flow inside a liquid slug, and therefore enhances heat transfer. It is shown that the heat transfer rate is strongly dependent on the flow pattern, i.e., the slug length and the flow rate of each of gas and liquid. The whole flow field is modelled as an adherent liquid film, above which the gas and liquid slugs alternately pass. Since the heat capacity and conductivity of gas phase are negligibly small, while the liquid film is sufficiently thin, the overall heat transfer can be deduced as one-dimensional unsteady heat conduction inside the liquid film with a time-dependent heat transfer rate at the interface between the film and the slug regions. We propose a heat transfer model as a function of parameters representing the flow pattern and assess it in comparison with the present numerical results. © 2009 Elsevier Inc. All rights reserved.
Lu D.,China General Nuclear Power Group |
Xiao Z.,Nuclear Power Institute of China |
Chen B.,Nuclear Power Institute of China
Nuclear Engineering and Design | Year: 2010
Natural circulation is one of the most important thermal-hydraulic phenomena that makes the fluid flow along a closed loop without any external driving force. With this merit, it is adopted by the passive heat removal system to bring the residual heat out of the core at accidents, and by the primary system of some new conceptual reactors instead of pumps to drive the coolant in the loop at operation. To investigate the reactor natural circulation and verify system thermal-hydraulic codes, it is a way to construct an integrated effect test facility and perform experiments on it with the scaling criteria. With one-dimensional assumption, the natural circulation system was simplified as the heat source, heat sink and pipes, and described by two groups of equations independently for the single-phase and two-phase flow conditions. Based on these equations, a set of non-dimensional equations were derived and the criteria were obtained both applicable for single-phase and two-phase natural circulation. According to these criteria, the practical application was analyzed and discussed. In the paper, the property similarity was strongly suggested in most cases. Though equal height simulation was widely used in the past, the reduced height simulation is a good way to reproduce three-dimensional (3D) phenomena that are of concern in the investigation. The CHF simulation is not suggested. The mass of metal and its distribution is of concern instead of heat transfer at transient simulation. © 2010 Elsevier B.V. All rights reserved.
Ji S.,China General Nuclear Power Group
9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015 | Year: 2015
This paper focuses on the design and modernization of nuclear power plant Main Control Room (MCR) and Human-System Interface (HSI) in LINGAO NPP units 3&4 in China. Modernization of old I&C system and components, using new digital I&C system and equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety, is a major improvement in the LINGAO NPP units 3&4. Any modernization for Control Room such as Backup-Panel(BUP), State Oriented Procedures (SOP), Large Display Panel (LDP), Computerized-base procedures, Advanced alarm system, Safety Parameter Display system(SPDS)..., that affects what information the operator sees or the system's response to a control input must be empirically evaluated to ensure that the new design does not compromise HSI effectiveness. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. This methodological approach will be used in new nuclear power plant, and also used in modernizing I&C system in currently operative nuclear power plants, in addition to meeting safety requirements and the plant's operational requirements, to improve costeffective plant and human performance and to reduce likelihood of human errors, to gain maximum benefit of the implemented technology and to increase the performance, resulting in improved plant safety, availability, reliability, and cost-effective operation.
China General Nuclear Power Group | Date: 2011-11-25
A cement curing formulation and curing method for high-level radioactive boron waste resins from a nuclear reactor. The curing formulation comprises the following raw materials: cement, lime, water, curing aids and additives. The curing method comprises: (1) weighing the raw materials and the high-level radioactive boron waste resins, and adding lime into a curing container; (2) then adding the high-level radioactive boron waste resins; (3) feeding other raw materials under stirring; (4) adding the cement and supplementing water depending on the moisture state of the cement, and stirring until uniform; and (5) standing and maintaining after stirring until uniform. The curing formulation has the features of a high curing containment rate, high strength of the cured body, better water resistance, better freeze-thaw resistance, and low radioactive leakage.