scholarly journals Influence of the service water system at the Kola Nuclear Power Plant on the heavy metals content in Lake Imandra

2020 ◽  
Vol 26 (2) ◽  
pp. 93-103
Author(s):  
S. S. Sandimirov ◽  
Keyword(s):  
Heavy Metals ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Water System ◽  
Service Water ◽  
Lake Imandra

Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit

2020 ◽  
Author(s):  
Shengtao Zhang ◽  
Ke Yi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Heat Sink ◽  
Nuclear Power ◽  
Cooling System ◽  
Water System ◽  
Total Loss ◽  
Operating Strategy ◽  
Service Water ◽  
Essential Service

Abstract Essential Service Water System (WES) is part of the nuclear power plant cooling system which provides the final heat sink for nuclear power plants. Therefore, WES must operate stably, safely and reliably for a long time. The total loss of WES accident is a design extended condition and will result in the loss of the final heat sink of the unit. The consequences of the accident are severe. In order to deal with the accident quickly and effectively and ensure the safety and economics of the power plant in accident condition, it’s necessary to formulate corresponding treatment strategy to deal with the transient. This paper developed a strategy for dealing with the total loss of WES with Residual Heat Removal System (RHR) not connected condition in Generation III nuclear power plant. The structure of the WES system and the types of failures that may occur are analyzed, and thus the symptoms of the faults are obtained and the entry conditions for the operating strategy are determined. The effect of faults on unit equipment and safety functions and the impact on nuclear steam supply system (NSSS) control are analyzed in this paper. Combined with the unit design, the system and equipment for controlling and mitigating related safety functions are analyzed, and the mitigation method and the fallback strategy of the fault are determined. Thereby a complete operating strategy of total loss of WES with RHR not connected is obtained. In addition, this paper analyzes and evaluates the operating strategy by simulating thermal hydraulic calculation for the first time. The results show that without staff intervention Component Cooling System (WCC) temperature reached 55°C limits after running a few minutes. Based on the intervention of the operating strategy proposed in this paper, WCC temperature reached the 55°C limits when the unit was operated at about 4 hours and 55 minutes. The result shows that and the strategy can effectively alleviate the failure and provide sufficient intervention time for the operator to bring the unit to a safe state.

The Root Cause Analysis of the Bolt Fracture in the Nuclear Power Plant Essential Service Water System

2017 ◽  
Author(s):  
Li Nan ◽  
Lao Yi ◽  
Che Yinhui
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Water System ◽  
Element Distribution ◽  
Material Microstructure ◽  
Root Cause ◽  
Check Calculation ◽  
Service Water ◽  
Essential Service

When inspecting in the nuclear power plant, the bolt of the 001/004 pump in Essential Service Water system was found fracture. The bolt in 001 pump had ever fractured before, and it had been replaced. In this paper, the material, microstructure, energy dispersive spectrometry and mechanical check calculation of the bolt are analyzed. The result shows, the bolt breakage is for stress corrosion cracking, the corrosion element is Cl−. When the martensitic stainless steel is in the heat treatment, the temperature is improper control, which causing the Cr element distribution changed. So the ability of material to resist corrosion becomes poor which is the root cause of the bolt fracture.

Design of Condenser Cooling Water System for a Nuclear Power Plant Located on a Large Estuary

1970 ◽  
Vol 92 (2) ◽  
pp. 150-156 ◽  
Author(s):  
F. J. Jeffers ◽  
J. C. Geyer ◽  
L. C. Neale
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Water System ◽  
Cooling Water ◽  
Aquatic Life ◽  
Cooling Water System ◽  
Dispersion Patterns ◽  
State Water ◽  
Jet Theory

A coordinated program is described for developing information needed for designing a condenser cooling water system for a nuclear power plant located on a large estuary to meet State water quality standards and minimize any adverse effects on aquatic life. The paper discusses estuarine conditions pertinent to the design of the intake and discharge structures, the heat assimilative capacity of the estuary, application of the momentum jet theory to the condenser cooling water discharges, and hydraulic model investigations to determine mixing and dispersion patterns.

Distribution of heavy metals around the Barakah nuclear power plant in the United Arab Emirates

2017 ◽  
Vol 24 (24) ◽  
pp. 19835-19851
Author(s):  
Mouza Rashid Al Rashdi ◽  
Sulaiman Alaabed ◽  
Mohamed El Tokhi ◽  
Fares M. Howari ◽  
Walid El Mowafi ◽  
...  
Keyword(s):  
Heavy Metals ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
United Arab Emirates ◽  
Nuclear Power

Ultrasonic Inspection of Large Diameter Polyethylene Pipe Used in Nuclear Power Plant

2014 ◽  
Author(s):  
Jianfeng Shi ◽  
Dongsheng Hou ◽  
Weican Guo ◽  
Yaoda Zhou ◽  
Xia Chen ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Large Diameter ◽  
Ultrasonic Inspection ◽  
Water System ◽  
Cooling Water ◽  
Operating Pressure ◽  
Traditional Natural

Polyethylene (PE) pipe has many advantages such as good flexibility, corrosion resistance and long service life. It has been introduced into nuclear power plants for transportation of cooling water both in U.S. and Europe. Recently, one Chinese nuclear power plant in Zhejiang Province also introduced four polyethylene pipelines in essential cooling water system with operating pressure of 0.6MPa and operating temperature of no more than 60°C. The PE pipes used in this nuclear power plant are DN762 SDR9 (30in OD, 3.3in wall), which are much larger and thicker than traditional natural gas PE pipe. As the pipe wall is so thick that the ultrasonic phased array instrument used in inspection of PE pipe with diameter less than 400mm has been improved. Results of field inspection in the Sanmen nuclear plant are reported, and the presented ultrasonic inspection technique proves to be effective for high density polyethylene (HDPE) pipe of large size in nuclear power plant.

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