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Patent
China General Nuclear Power Group, Daya Bay Nuclear Power Operations, Management Co. and China Institute for Radiation Protection | Date: 2013-04-17

Disclosed are a reagent for testing the purification capacity of a radioactive gas in a nuclear power plant, preparation method thereof and an iodide filter testing equipment using this reagent. The reagent is prepared by mixing methyl phosphate compound or dimethyl acetal compound, acetonitrile, trimethyl chlorosilane and radioactive iodine sources and carrying out a reaction at a temperature of 20C-50 C under an inert gas for 10-40 min. The prepared products except methyl iodide are non-toxic or little toxic to the nuclear grade impregnated activated carbon in the iodide filter.


Patent
China General Nuclear Power Group, Daya Bay Nuclear Power Operations and Management Co. | Date: 2013-10-16

The invention is applicable to the field of nuclear power control, which provides a digitalized control system (DCS) of a nuclear power unit, and an information processing method and device for the DCS. Task information, digitalized operation list (2) information corresponding to the task information, and supporting interface (3) information are outputted by the main body of a program (1). The digitalized operation list (2) corresponding to a specified task is searched for according to the programs main body (1). The detailed information of the task, the device information according to the detailed information of the, and task link information are outputted by the found digitalized operation list (2). The digitalized operation list (2) issues a linking instruction to the supporting interface (3). The supporting interface (3) receiving the linking instruction outputs cross-system monitoring parameters and operation instructions. Digitalized processing of the overall program of the nuclear power unit, overcomes deficiencies of DCS visibility. The running efficiency of the overall program of the nuclear power unit is increased, and the advantage of information processing of the DCS is fully employed.


Patent
China General Nuclear Power Group, Daya Bay Nuclear Power Operations, Management Co., Guangdong Nuclear Power Joint Venture Co. and Lingao Nuclear Power Co. | Date: 2014-10-01

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. The curing method has low requirements on the processes, is simple to operate and easy to implement, and can satisfy the demands of on-site curing.


Patent
China General Nuclear Power Group, Daya Bay Nuclear Power Operations and Management Co. | Date: 2013-06-05

Method and system for supplying emergency power to nuclear power plant, wherein the method includes, providing accumulator battery system, connected to emergency bus, the accumulator battery system is monitored by online monitoring system; in case of power loss of electrical devices of the nuclear power plant, the online monitoring system starts the accumulator battery system to provide power supply to the electrical devices of the nuclear power plant via the emergency bus. The present application is adapt to the key technologies and battery management technologies of million kilowatt-class advanced pressurized water reactor nuclear power plant, facilitating to improve the safety of the nuclear power plant in case of serious natural disasters beyond design working conditions.


Shi J.,Suzhou Nuclear Power Institution Co. | Zeng Q.,Daya Bay Nuclear Power Operations and Management Co.
Advanced Materials Research | Year: 2012

The Ageing mechanisms of electromagnetic relay were discussed. And the key ageing indicators were found out. Then, the test methods of ageing indicators were introduced. After that, a method to evaluate the lifetime for the coil of electromagnetic relay was proposed. Accelerated ageing test was conducted to the coils, and the key ageing indicators were collected periodically. According to those test data, the ageing condition and lifetime were evaluated. In the end of the paper, examples about assessing the ageing condition and lifetime were given separately. © (2012) Trans Tech Publications, Switzerland.


Wang Q.,Daya Bay Nuclear Power Operations and Management Co. | Liu G.,PLA Air Force Aviation University | Shi Y.,Jilin University
Lecture Notes in Electrical Engineering | Year: 2012

This paper describes a technology of multi-dim-small-target detection. Two-dimensional (2-D) adaptive filtering and multi-dim-small-target segmentation algorithm is suggested to enhance 2-D signals of small spatial extent embedded in additive white Gaussian noise(AWGN) and detect multi-dim-small-target in complex background. The coefficients of the adaptive filter converge to a special 2-D slice of the fourth-order cumulant function of the input signal. The 2-D filter is called the 2-D cumulant-based adaptive enhancer (2DCBAE). And the dim-small-target segmentation algorithm is combining some theory, such as the wavelet energy transformation, image reconstruction, data fusion and self-adaptive threshold segmentation. © 2012 Springer-Verlag Berlin Heidelberg.


Guo C.,Daya Bay Nuclear Power Operations and Management Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2010

In order to analyze the differences between the Anticipated Transient Without Reactor Trip (ATWT) and other reactor protection methods, this paper analyzes in detail the realizing means of ATWT and the effect of lost of power supply on the units based on Daya Bay and Ling'ao Nuclear Power Stations by system wiring diagram. Based on the comprehensive analysis, this paper proposes the sequence for powering when recovering the power source after ATWT power supply (LCC/LNE) loss for Daya Bay and Ling'ao Nuclear Power Stations.


Sun X.,University of Tokyo | Sakai M.,University of Tokyo | Shibata K.,University of Tokyo | Tochigi Y.,Daya Bay Nuclear Power Operations and Management Co. | Fujiwara H.,Daya Bay Nuclear Power Operations and Management Co.
Nuclear Engineering and Design | Year: 2012

In Japan, it is planned to use vitrification to immobilize high level radioactive liquid waste (HLLW) obtained from the nuclear reprocessing process. In the vitrification process, the HLLW will be mixed with molten glass in a joule-heated glass melter. The molten glass is then poured into a canister through a nozzle at the bottom of the melter. When some abnormalities occurred, feature of the discharged flow become different from that in normal conditions. We cannot observe the state of the molten glass inside the melter directly because of the severe environment. Accordingly, we cannot investigate the cause when the abnormalities occurred. Hence, numerical simulation of the discharged flow becomes important to understand and recover from operational problems or abnormalities with the glass melter. However, existing numerical models of the glass melter do not really simulate the discharged glass flow. In the present study, we introduce a new algorithm into an existing Lagrangian approach to efficiently simulate the discharged glass flow. To verify the model, 3D simulations were performed on a real scale system and got compared with the results of experimental validation tests. The simulation results show good agreement with the experimental results. Consequently, the new Lagrangian approach accurately simulates the molten glass flow. © 2012 Elsevier B.V. All rights reserved.


Guo C.,Daya Bay Nuclear Power Operations and Management Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2013

This paper comprehensively analyzes PWR steam generator heat transfer tube rupture accident (SGTR), and summarizes the accident processing key strategies in the terms of detection means and event nuclear safety analysis. It analyzes the accident processing difficulty and key risk. Taking the America Indian point2 nuclear power plant SGTR as an example, the events de tailed process is described and the corresponding operation experience is given.


Gao P.,Daya Bay Nuclear Power Operations and Management Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2013

The root cause of the high on-line vibration measurement of the nuclear power half-speed turbo-generator is studied, and the result shows that the first natural frequency of the sensor support setting isclose to the forth times harmonic wave of the generator speed frequency, that is the root reason of the high on-line vibration. This paper uses the three-dimension modeling software to make fixture mode of the sensor support setting, and utilize finite element analysis (FEA) software to analyze and calculate its frequncy characteristics. Two schemes are offered by adding a mass block or increasing the stiffness of the sensor support setting, that change the natural frequency. So the resonance is avoided, and the authenticity and effectiveness of the on-line vibration is ensured.

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