Fujian Fuqing Nuclear Power Co.

Fuqing, China

Fujian Fuqing Nuclear Power Co.

Fuqing, China
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Liu Z.,Fujian Fuqing Nuclear Power Co. | Song M.,Fujian Fuqing Nuclear Power Co. | Wu J.,Fujian Fuqing Nuclear Power Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2017

As the computer technology was widely used in nuclear power plants, a lot of unpredictable problems happened in the process of DCS(Distributed Control System) replacing the traditional relay rack. In this paper, considering the practical situation of Fuqing nuclear power DCS project, the typical problems in non-safety class of DCS software, which appeared during testing and commissioning process, are analyzed and the solution plan is proposed to obtain the experiences for the operation and commissioning activities in the future. © 2017, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.


Chen F.,Fujian Fuqing Nuclear Power Co. | Liu J.,Fujian Fuqing Nuclear Power Co. | Ye Q.,Fujian Fuqing Nuclear Power Co. | Wang S.,Fujian Fuqing Nuclear Power Co. | And 2 more authors.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2017

Before the loading of nuclear fuels in a nuclear power plant, in the underwater test of the conveyor of fuel transfer system, we found that the conveyor failed to drive when it moved to K side (fuel plant side) at the travel end. In this paper, the causes are analyzed and solved in terms of the structure of conveyor of fuel transfer system and upender, and the content of the preventive maintenance project is further optimized. © 2017, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.


Qiao Z.,Fujian Fuqing Nuclear Power Co. | Zhao X.,Fujian Fuqing Nuclear Power Co. | Chen P.,Fujian Fuqing Nuclear Power Co. | Lin J.,Fujian Fuqing Nuclear Power Co.
Corrosion Science and Protection Technology | Year: 2017

There are many seawater pipelines in a nuclear power plant. As seawater with high corrosive property, in spite of anti- corrosion measures such as coating, rubber lining and sacrificial anode have already applied to pipelines since the design, but corrosion occurs endlessly, especially perforation of the pipelines. An analysis on the case history of the corrosion induced perforation of pipeline of the auxiliary cooling water system at Fuqing nuclear power plant has been made, and it follows that the corrosion case may be ascribed to the poor construction quality, the insufficient protection supplied by sacrificial anode and the galvanic corrosion induced by the coupling of the perforated pipe with the conjoint heat exchanger. The findings and conclusions may be a useful reference for the selection of corrosion protection countermeasures as well as the further design and construction of the seawater pipeline. © 2017, Chinese Academy of Sciences. All rights reserved.


Wei T.,Nuclear Power Institute of China | Lin J.,Fujian Fuqing Nuclear Power Co. | Long C.,Nuclear Power Institute of China | Chen H.,Nuclear Power Institute of China
Jinshu Xuebao/Acta Metallurgica Sinica | Year: 2016

Advanced boiling water reactors (ABWRS) show optimistic application prospect in the future. However, in these reactors, influence of dissolved oxygen (DO) on the corrosion rate of zirconium fuel claddings should be seriously considered. In this work, the effect of the dissolved oxygen (DO) on the corrosion behaviors of Zr-4, N18 (Zr-1.0Sn-0.3Nb-0.3Fe-0.1Cr) and N36 (Zr-1.0Sn-1.0Nb-0.3Fe) alloys in 400℃ and 10.3 MPa steam was investigated. A recirculation loop was used to control the DO level at about 0.1×10-6 and 1.0×10-6, respectively. The results showed that, under the two DO level conditions, N18 had almost the same weight gain as Zr-4 after exposure for 90 d, and N36 had the highest weight gain. In the initial period of the corrosion test, the three alloys had lower weight gain under higher DO level condition. With the increase of exposure time, the weight gain under 1.0×10-6DO level exceeded gradually the weight gain under 0.1×10-6 level for each alloy, and the time needed for exceeding was significantly shorter for the alloy with higher Nb content. © All right reserved.


Yan C.,University of Science and Technology Beijing | Yan C.,China Institute of Atomic Energy | Wang R.,Suzhou Nuclear Power Research Institute | Dai X.,Fujian Fuqing Nuclear Power Co. | And 4 more authors.
Journal of Nuclear Materials | Year: 2016

Irradiation hardening behavior of Zr-1Nb was examined by nanoindentation, slow positron annihilation technique, transmission electron microscopy and coplanar extremely asymmetric X-ray diffraction technique. Samples were irradiated at a dose rate of 2.78 × 10-4 dpa/s to peak doses of 0.15, 0.5, 1.5 and 2.5 dpa with 6.37 MeV Xe26+ ion beam at room temperature. The increase in hardness as a function of dose followed a power law expression with the exponent of 0.46. With increasing irradiation dose, more mono-, di- and trivacancies were induced, but their concentration remained constant once formed due to the equilibrium between the formation and recombination of vacancy type clusters during irradiation. Meanwhile, the dislocation loops were also introduced and their linear density increased with dose. The dislocation loops played an important role in the irradiation hardening behavior. But the exact contribution of each microstructural components to the overall hardness still needs further study. © 2016 Elsevier B.V. All rights reserved.


Li S.,University of Science and Technology Beijing | Wang Y.,University of Science and Technology Beijing | Dai X.,Fujian Fuqing Nuclear Power Co. | Liu F.,Chalmers University of Technology | And 2 more authors.
Journal of Nuclear Materials | Year: 2016

The ion irradiation hardening behaviors of Fe-9 wt% Cr and Fe-20 wt% Cr model alloys were investigated by nanoindentation technique. The specimens were irradiated with 3 MeV Fe11+ ions at room temperature up to 1 and 5 dpa for Fe-9Cr alloy and 1 and 2.5 for Fe-20Cr alloy. The ratio of average hardness in the same depth of irradiated and unirradiated (Hirr. av/Hunirr. av) was used to determine the critical indentation depth hcrit to eliminate the softer substrate effect. The Nix-Gao model was used to explain the indentation size effect. Irradiation hardening is clearly observed in both Fe-9Cr alloy and Fe-20Cr alloy after ion irradiation. The differences of ISE and irradiation hardening behaviors between Fe-9Cr and Fe-20Cr alloys are considered to be due to their different microstructures and microstructural evolution under ion irradiation. © 2016 Elsevier B.V.


Gu J.,Fujian Fuqing Nuclear Power Co. | Li J.,Fujian Fuqing Nuclear Power Co. | Jiang Y.,Fujian Fuqing Nuclear Power Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

In the practices of the nuclear power plant construction, unpractical prescriptions in equipment technical specification will result in much more unnecessary non-conformance items which meet RCC-M., Based on the engineering experience, this paper proposed three moderate application principles from three aspects, which can more specifically regulate the behavior of the people in this field to some extent. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.


Yang S.,Fujian Fuqing Nuclear Power Co. | Liu L.,Fujian Fuqing Nuclear Power Co. | Huang X.,Fujian Fuqing Nuclear Power Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2014

In the domestic and abroad standards, the grounding capacitive current limitation in the non-grounding electric auxiliary system is less than 10 A. Limiting capacitive current in the standard aims to speed up the arc extinguishing, to reduce the duration of arc over-voltage, but not to prevent the arc producing. The arc over-voltage harm is related to the multiple, frequency and duration of the over-voltage. When the insulation vulnerabilities appear in the equipment, the arc over-voltage may result in insulation vulnerabilities of the electrical equipment breakdown, which leads to multiple short-circuit accidents. The cable connector, accessory and electromotor winding are all insulation vulnerabilities. Setting the arc suppression coil which can counteract the grounding capacitive current makes the arc vanish quickly. Using the casting bus which remarkably reduces the ground capacitance of the electric transmission line makes the equipment safer. ©, 2014, Yuan Zi Neng Chuban She. All right reserved.


Liu Z.-S.,Fujian Fuqing Nuclear Power Co. | Huang H.,Fujian Fuqing Nuclear Power Co.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2013

Taking Phase I Fujian Fuqing nuclear power plant project as a reference, functions and composition of PWR Nuclear Power Plant radiation monitoring system operated in our country are introduced firstly in this article. Then development tendencies, as well as the design improvements are described in detail in aspects as airborne radioactive material sediment loss in the sampling pipeline, standard calibration methods for airborne sampling monitors, detection technology for leakage of primary circuits, network topology, high humidity noble gas monitoring technology, and site monitoring technology, etc.


Yao W.,Fujian Fuqing Nuclear Power Co. | Guo Y.-S.,Fujian Fuqing Nuclear Power Co. | Wang Y.,Fujian Fuqing Nuclear Power Co. | Xu Y.,Fujian Fuqing Nuclear Power Co.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2015

The structure of FuQing nuclear power Reactor protection system was introduced. Pointing to the complex of the system logic structure, urgency of the Commissioning time, Visual Studio. net C# was used in the development the simulation software based on logic diagram of FuQing nuclear power reactor protection system, making the structure of the RPS System more clear and speeding up the commissioning process. The TCP/IP communication protocol was used to communicate the DCS data acquired system. ACCESS database was used to save, search, and maintenance the system data. Finally through the software testing, it was achieved the purpose of the system simulation. © 2015, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.

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