Temperature Field Analysis for Freezing Sealing Structure of Sodium Gate Valve in China Experiment Fast Reactor (CEFR)

2013 ◽  
Author(s):  
Lina Hu ◽  
Huajin Yu ◽  
Mingyu Lv
Keyword(s):  
Temperature Field ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Large Scale ◽  
Gate Valve ◽  
Structure Design ◽  
Field Analysis ◽  
Power Station ◽  
Experimental Relation ◽  
Simulation Results

In order to achieve the localization of the large-scale sodium gate valve in fast reactor nuclear power station, this paper use fluid software FLUEN, using two different methods, analysis temperature field of sodium gate valve freezing sealing structure of CEFR. The first method is to establish air model; the second method is to making use of experimental relation to calculate surface coefficient of heat transfer to simulate temperature field of freezing sealing structure of sodium gate valve in CEFR. Compared with measuring results on-site, simulation results of the first method have error within 10%. Therefore, it is feasible that simulating temperature field of freezing sealing structure with this method. That will promote structure design of freezing sealing of sodium gate valve for large fast rector power plant.

Temperature Field Analysis and Cooling Structure Design of Ironless Permanent Magnet Synchronous Linear Motor

2021 ◽  
Vol 14 ◽  
Author(s):  
Xiaoting Lu ◽  
Yang Li ◽  
Zailiang Chen
Keyword(s):  
Temperature Field ◽  
Permanent Magnet ◽  
Heat Loss ◽  
Linear Motor ◽  
Structure Design ◽  
Servo Control ◽  
Field Analysis ◽  
Temperature Fields ◽  
Water Cooling ◽  
Linear Motors

Objective: Ironless, permanent magnet, synchronous linear (IPMSL) motors are applied widely in precision servo control for the nonexistence of cogging forces and comparatively small fluctuations in thrust and speed. Method: The air and water cooling structures are designed by assuming the heat loss in the motor operations is the source for the distribution of the temperature field in the analysis under natural cooling. Conclusion: The temperature fields of the linear motor under the two cooling modes are compared and analyzed, which helps monitor the temperature of linear motors during development and operations.

Automation of the electric heating system in a nuclear power station with a fast reactor

1975 ◽  
Vol 39 (2) ◽  
pp. 667-669
Author(s):  
A. N. Mitropol'skii ◽  
I. Kh. Tsukerman ◽  
A. A. Petrenko
Keyword(s):  
Nuclear Power Station ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Electric Heating ◽  
Heating System ◽  
Power Station

Guangdong Electric Power Sustainable Development Strategy

2005 ◽  
Author(s):  
Bin Ma ◽  
Hua Yang ◽  
Hongkai Liao
Keyword(s):  
Sustainable Development ◽  
Development Strategy ◽  
Flue Gas ◽  
Nuclear Power ◽  
Large Scale ◽  
Electricity Consumption ◽  
Guangdong Province ◽  
Power Station ◽  
Existing Problems ◽  
The Social

This article introduces the current situation of Guangdong energy supply and electricity consumption, analyses the electricity structure and existing problems and points out that in order to meet the social demand for electricity and sustainable development of Guangdong province, it must expand the scale of West-East electricity transmission, build large-scale super-critical generation units, accelerate building nuclear power station, build LNG generation units in the load centers, promote the growth of wind- electricity, develop flue gas desurlphurization and denitrification technology, etc.

scholarly journals Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

2013 ◽  
Vol 2013 ◽  
pp. 1-18 ◽  
Author(s):  
Yeong-il Kim ◽  
Yong Bum Lee ◽  
Chan Bock Lee ◽  
Jinwook Chang ◽  
Chiwoong Choi
Keyword(s):  
Fast Reactor ◽  
Electricity Generation ◽  
Nuclear Power ◽  
Large Scale ◽  
Development Program ◽  
Energy Resources ◽  
Test Facility ◽  
Current Status ◽  
Hydraulic Test ◽  
Design Concepts

Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.

Temperature Field Analysis on Cooling Stave Material and Stave Body

2011 ◽  
Vol 130-134 ◽  
pp. 931-934
Author(s):  
Fang Wei ◽  
Jiang Chang
Keyword(s):  
Heat Transfer ◽  
Temperature Field ◽  
Blast Furnace ◽  
Structure Design ◽  
Field Analysis ◽  
Temperature Fields ◽  
Temperature Field Distribution ◽  
The Relationship ◽  
Account Temperature ◽  
General Method

The cooling stave longevity is the most important factor to affect the blast furnace life. In this paper the cooling stave model was built by use of software ANSYS. With boundary conditions of heat transfer of cooling stave fully taken into account, temperature fields of cooling stave made of different materials are analyzed. The analysis results showed the relationship between the different cooling stave materials and temperature field distribution of stave body. A general method of selecting cooling stave material and structure design for longevity design of cooling stave was developed.

Researches on the Simulation of the Degasifying Column Used in Nuclear Power Plant

2013 ◽  
Author(s):  
Jianhua Xie ◽  
Quanliu Ye ◽  
Jinchun Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Aspen Plus ◽  
The Other ◽  
Power Station ◽  
Simplified Models ◽  
Simulation Results ◽  
Aspen Simulation

The degasifying column is an important unit in nuclear power station. In order to verify the performance of the column, the degasifying process has been simulated by using the well-known software ASPEN Plus and on a basis of some proper hypothesizes and simplified models. Degasifying column is found that it has good capability on taking out key components such as krypton and oxygen from reactor coolant. On the other side, it’s difficult to carry out radioactive gas experiment on site which is seriously enslaved to the potential radioactive harm on operators. Simulation by using ASPEN Plus is a good way to solve this problem. Furthermore, three kinds of experiments such as ASPEN simulation, deoxidation experiment and radioactive gas experiment on site which are used for validating the performance of column are compared. The comparison shows that ASPEN simulation has less risk and less costs, but the simulation results are more exact and credible. Moreover, the debugging process of the column can be inducted and improved according to the simulation.

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