Haiyanmiao, China
Haiyanmiao, China

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Guo P.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

Based on the collection and statistical analysis of the radiation monitoring instrument calibration data, and taking the typical GIM204 gamma dose rate monitoring device as an example, the feasibility is demonstrated by the experience feedback method, to adapt to the implementation of the refueling scheme for a long period of time in Tianwan nuclear power station. Studies have shown that when the calibration cycle of GIM204 is extended from1 year to 1.5 year, the relative calibration error does not exceed the allowable values, and satisfies the requirement on refueling cycle extension. ©, 2015, Editorial Office of Nuclear Power Engineering. All right reserved.


Peng F.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

Fuel assembly gripper driving circuit is a key part of the refueling machine. Its reliability has great significance for safety and stability of refueling operation. A number of tripping faults have occurred since the operation of the refueling machine No.1 and No.2 of Qinshan nuclear power plant II, and it has a certain impact on the refueling operation. With gripper driving circuit as the research object, considering the fault phenomenon and the maintenance experiences, the reasons of key components defect were analyzed in detail, the troubleshooting methods and solutions were summarized, and the measures to solve the problem was provided. ©, 2015, Editorial Office of Nuclear Power Engineering. All right reserved.


Kong W.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

Service water system operation requirements and circulate water system maintenance needs are analyzed, and it is determined that the circulate water system maintenance will result in the availability of service water pumps. Solutions are proposed to resolve the conflicts between the circulate water system maintenance and the service water system availability, that will improve the safety and economy of the plant. ©, 2015, Editorial Office of Nuclear Power Engineering. All right reserved.


Guo P.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

False alarm problem of radioactive iodine activity monitor during commissioning in nuclear plant is analyzed and studied. Results show that the instrument background noise, ambient gamma radiation field and other non nuclide measurement statistics will cause the measured value distortion; the using of the 131I detecting efficiency to calculate the 131I to 135I total radioactive iodine volume activity will cause the distortion of the measured results. Through the analysis of the reasonability of the set area of the radioactive iodine monitor energy window, and to change the measurement window energy 100~2000 keV to 310~410 keV, only 131I is monitored. After the implementation of this program, the instrumentation values are accurate and no false alarm occurs. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.


Sun J.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

In the pressurized water reactor which uses ammonia to adjust the feedwater pH, the high PH control method is usually used to inhibit the flow accelerated corrosion (FAC) in the secondary system. But the increasing Ammonia concentration will shorten the lifetime of the resin in the steam generator blowdown system demineralizer, which will lead to the increasing of waste, heavy loading, and operation cost. By the ammonia-saturated operation test of the resin in the steam generator blowdown system demineralizer in Qinshan phase II, we found that the ammonia-saturated operation is feasible; and it is an effective method to balance the demand of high PH value and the lifetime of demineralizer resin. And we prefer to use 2 demineralize systems together, one with ammonia-saturated operation and another one with hydrogen operation. © 2015, Yuan Zi Neng Chuban She. All right reserved.


Gao Y.,Nuclear Power Qinshan Co. | Zhu Y.-L.,Nuclear Power Qinshan Co.
Nuclear Science and Techniques | Year: 2014

In order to monitor the diffusion and deposition of radioactive plume in Qinshan area after Fukushima nuclear accident, a continuous air sampling was did from March 25 to May 6. A trace of 134Cs and 131I were detected in the period. Results of conventional environmental radiation monitoring also showed that the specific activity of 90Sr and 137Cs in environmental samples had some abnormal changes in 2011 which almost felt back to normal level in 2012. Although there is no abnormal change on environmental radiation level of Qinshan area till now, the influence caused by Fukushima nuclear accident should be paid continuously attention in future by radiation monitoring. © 2014, Science Press. All rights reserved.


Zhang G.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

During the commissioning of the thermostatic and humid static air conditioning unit (THACU), four THACUs in MCR and computer room are turned on and off frequently, which will threaten the safety and life span of the units. Meanwhile, when the four THACUs are in operation, the heater is running at 100% power to keep the environment under a constant temperature, which causes a serious waste of electrical power. Through the alteration, the problems are solved and the THACUs can operate properly and stably. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.


Li Z.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

After the loss of coolant accident (LOCA) for preventing low pressure safety injection pump or a security shell spray pump function complete failure (H4) beyond design basis accident, design the H4 pipeline, in H4 conditions using still available low pressure safety injection pump or containment spray pump to realize the functions of the reactor core, long-term cooling. Of H4 condition under the safety injection system (RIS) and the containment spray system (EAS) reserve for test, by selecting features: low and high performance of the low pressure safety injection pump and low characteristic of the containment spray pump to verify the parameters in accident conditions can still meet the requirements, at the same time verified to the reactor coolant system (RCP) cooling system, thermal injection, outlet flow of the pump meet the Qinshan nuclear power plant expansion project (Fang Shan nuclear power project) debugging safety standards in the outline. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.


Xu Z.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

Residual Heat Removal System (RRA) can be used to maintain the reactor coolant temperature at cold shutdown conditions to offer the time required for the refueling and maintenance operations. In the maintenance in the cold shutdown condition (with the fuel in the reactor), this system will keep the reactor coolant temperature less than 60 centigrade for the repairman to get into the manhole of any one of the steam generators and maintain the reactor cooling. In this test, it requires to prove that in this condition the reactor coolant does not enter the steam generator bottom head to result in additional staff radioactive contamination when the primary loop high level alarm occurs. The residual heat removal pump is required to run without cavitation even at its designed maximum flow rate when the primary loop low level alarm occurs. The level of the primary loop should change slowly to avoid the instrument false when the RCP300MN is put into use during the maintenance cold shutdown condition. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.


Wang C.,Nuclear Power Qinshan Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

This essay introduces commissioning tests after replacement of main feed water control valve of operating unit, analyzes risks of commissioning tests and provides counter-measures. It also mainly stresses problems emerged from commissioning tests of main feed water control valve as well as their treatment. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.

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