Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action

2018 ◽  
Author(s):  
Li Yan ◽  
Hu Wenjun ◽  
Ren Lixia
Keyword(s):  
Numerical Simulation ◽  
Fast Reactor ◽  
Simulation Method ◽  
Drive Mechanism ◽  
Pipe System ◽  
The Core ◽  
Hydraulic Method ◽  
Drop Time ◽  
China Experimental Fast Reactor ◽  
The Relationship

Safety rod and its drive mechanism is one of the shutdown systems in sodium-cooled fast reactor, which must be quickly inserted into the core to achieve emergency shutdown in the event of an accident. Therefore, it is necessary to study the falling process of safety rod. In this paper, the numerical simulation method is used to analyze the falling process of safety rod and its drive mechanism in China Experimental Fast Reactor. According to the flow path of the safety rod and its drive mechanism, the pipe system hydraulic method is used to model the safety rod and its drive mechanism and calculate the hydraulic force of the safety rod and its drive mechanism during the falling process. The relationship between time, displacement, velocity and acceleration is presented. The drop time of safety rod is calculated, which is compared with the experimental results. The factors that affect the drop process are analyzed and a sensitivity analysis is presented.

Numerical Simulation of the Stress Field of Thick 7B04 Aluminum Alloy Board during Continuous Manufacture Procedure

2007 ◽  
Vol 127 ◽  
pp. 259-264
Author(s):  
Hong Yuan Fang ◽  
Cheng Iei Fan
Keyword(s):  
Numerical Simulation ◽  
Aluminum Alloy ◽  
Stress Concentration ◽  
Stress Field ◽  
Solution Treatment ◽  
Simulation Method ◽  
The Core ◽  
Manufacturing Procedure ◽  
Continuous Manufacture ◽  
Simulation Results

Numerical simulation method is employed in the article to analyze the stress field of thick 7B04 aluminum alloy board during manufacturing procedure of solution treatment, calendaring and stretching. The simulation results show that the surface of the board endures compressive stress while the core segment endures tensile stress, and the distribution of the stress is very inhomogeneous. The calendaring procedure helps to decrease the stress and redistribute the stress uniformly, but it also leads to stress concentration at the two ends of the board, which engenders bad influence on the subsequent processing. The board deforms plastically when being stretched, thus the stress decreases greatly and is redistributed uniformly.

CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor

2018 ◽  
Author(s):  
Jing Chen ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
Kui Zhang ◽  
Mingjun Wang ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Power Distribution ◽  
Three Dimensional ◽  
Reactor Core ◽  
Heat Removal ◽  
The Core ◽  
Computational Fluid Dynamics Cfd ◽  
Heat Removal System ◽  
China Experimental Fast Reactor ◽  
Full Core

As the first developmental step of the sodium-cooled fast reactor (SFR) in China, the pool-type China Experimental Fast Reactor (CEFR) is equipped with the openings and inter-wrapper space in the core, which act as an important part of the decay heat removal system. The accurate prediction of coolant flow in the reactor core calls for complete three-dimensional calculations. In the present study, an investigation of thermal-hydraulic behaviors in a 180° full core model similar to that of CEFR was carried out using commercial Computational Fluid Dynamics (CFD) software. The actual geometries of the peripheral core baffle, fluid channels and narrow inter-wrapper gap were built up, and numerous subassemblies (SAs) were modeled as the porous medium with appropriate resistance and radial power distribution. First, the three-dimensional flow and temperature distributions in the full core under normal operating condition are obtained and quantitatively analyzed. And then the effect of inter-wrapper flow (IWF) on heat transfer performance is evaluated. In addition, the detailed flow path and direction in local inter-wrapper space including the internal and outlet regions are captured. This work can provide some valuable understanding of the core thermal-hydraulic phenomena for the research and design of SFRs.

Research on Relationship between Weight Filter Function and Stiffness Filter Function

2011 ◽  
Vol 411 ◽  
pp. 580-583
Author(s):  
Zhen Shang ◽  
Yun Kang Sui
Keyword(s):  
Numerical Simulation ◽  
Topology Optimization ◽  
Least Squares Method ◽  
Simulation Method ◽  
Homogenization Method ◽  
Structural Topology Optimization ◽  
Structural Topology ◽  
Filter Function ◽  
The Impact ◽  
The Relationship

Combined with the homogenization method and the least squares method, the filter function with the form of power function is studied in the Independent Continuum Map (ICM) method. Then, the numerical simulation method is used to study the relationship between a weight filter function and a stiffness filter function. Finally, the impact of the filtration function on the efficiency of topology optimization is showed by examples. It is important to further research structural topology optimization.

Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

2018 ◽  
Vol 4 (2) ◽  
Author(s):  
Xiong Wenbin ◽  
Xie Qin ◽  
Li Huwei ◽  
Yang Sengai ◽  
Mao Huan ◽  
...  
Keyword(s):  
Monte Carlo ◽  
International Atomic Energy Agency ◽  
Fast Reactor ◽  
Physical Parameters ◽  
Energy Agency ◽  
Safety Review ◽  
The Core ◽  
Calculation Results ◽  
Design Values ◽  
China Experimental Fast Reactor

The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.

Development of Numerical Estimation Method Using Spatial Connection Methodology for Thermal Striping in Upper Plenum of Reactor Vessel of an Advanced Loop-Type Sodium-Cooled Fast Reactor in Japan

2017 ◽  
Author(s):  
Masaaki Tanaka ◽  
Satoshi Murakami
Keyword(s):  
Numerical Simulation ◽  
Fast Reactor ◽  
Estimation Method ◽  
Local Area ◽  
Outer Side ◽  
Numerical Estimation ◽  
Analysis Model ◽  
Control Rod ◽  
The Core ◽  
Thermal Striping

Thermal striping on the core instrumentation plate (CIP) at the bottom of the upper internal structure (UIS) of an advanced loop-type sodium-cooled fast reactor in Japan (Advanced-SFR) has been numerically investigated. At the top of the core below the CIP, the sodium at high temperature flows out from the fuel subassemblies (FSs) and the sodium at low temperature flows out from the primary control rod (PCR) and backup control rod (BCR) channels, and also the radial blanket fuel subassemblies (RBFSs) at the outer side of the core. In order to predict the thermal striping on the CIP caused by mixing fluids at different temperatures from the FSs, the PCR and the BCR channels, and the RBFSs, a numerical estimation method using a spatial connection methodology between the upper plenum analysis and the local area analysis for the target area has been developed. By using the connection methodology, the numerical simulation considering the influence of the transversal flow in the UIS and the external flow around the UIS in the upper plenum can be performed to improve the accuracy of the estimation results. In this paper, the outline of the spatial connection methodology including data transfer technique from the upper plenum analysis to the local area analysis was described. As a validation process, numerical simulation of the water experiment using the test apparatus named TAFUT which was 1/3-scaled 1/6 partial model of the upper plenum of the Advanced-SFR was performed to confirm applicability of the spatial connection methodology to a practical thermal striping problem. The numerical result of temperature distribution was compared with the measured result in TAFUT experiment. Additionally, mesh sensitivity of the local area analysis model to the numerical results was indicated by using a small and a large area models in order to suggest an appropriate local area analysis model.

Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory

2017 ◽  
Author(s):  
Hu Xiao ◽  
Chen Xiao Liang
Keyword(s):  
Neutron Source ◽  
Fast Reactor ◽  
Thermal Power ◽  
Reactor Vessel ◽  
Monte Carlo Code ◽  
Construction Time ◽  
Mcnp Simulation ◽  
The Core ◽  
China Experimental Fast Reactor ◽  
Loading Scheme

An innovative small modular sodium cooled fast reactor called S1 is designed by China Institute of Atomic Energy (CIAE). As an encapsulated nuclear source with thermal power of 3MW, S1 is characterized by small volume, light weight, high safety and sound reliability. The S1 systems adopt modularization, by which the core will be loaded in a factory and filled with sodium, then shipped to the assembled onsite, thus the construction time for S1 can be substantially reduced. In this paper, the Monte Carlo code MCNP is used to calculate the loading scheme of S1. Considering factory’s special conditions for loading and active chemical property of sodium, a special loading pattern is adopted for S1 — loading fuel first, then sodium filling. Ensure that the neutron source and detectors are well matched during loading, and detector counting rate is no less than 2cps when only neutron source but no fuel exists in the core. Three positions where the 252Cf neutron source is placed are studied in this paper: (1) at the center of the core; (2) at the middle of outside core plane; (3) at the bottom of outside the reactor vessel. Through MCNP simulation calculations and comparison of large resulting data, it finds the neutron source should be reasonably placed at the bottom of the reactor vessel where 252Cf strength is 105 s−1 neutrons, and the ex-core detectors are distributed symmetrically at the center of outside core plane; the most befitting moderator material of detector surface is methacrylate-C5H8O3. In this paper, 1/N extrapolation method is used during loading and kinds of loading schemes have been studied with reference to the principles of China experimental fast reactor (CEFR) and regulations of relevant research reactors, and 5-batch loading scheme is finally chosen as the optimal loading scheme. S1 is prepared for sodium filling at 250 °C. It shows that neutron flux variation of core can be more reliably monitored when the ex-core detectors are placed about 120cm away from the center core through MCNP simulation calculation. Such arrangement can also meet the monitoring requirements for loading and sodium filling.

Effects of tool eccentralization on cement-bond-log measurements: Numerical and experimental results

Geophysics ◽  
2013 ◽  
Vol 78 (4) ◽  
pp. D181-D191 ◽  
Author(s):  
Ruo-Long Song ◽  
Ji-Sheng Liu ◽  
Xiu-Mei Lv ◽  
Xiu-Tian Yang ◽  
Ke-Xie Wang ◽  
...  
Keyword(s):  
Numerical Simulation ◽  
Finite Difference ◽  
Quality Evaluation ◽  
Horizontal Wells ◽  
Simulation Method ◽  
Experimental Results ◽  
Vertical Wells ◽  
The World ◽  
Fluid Channel ◽  
The Relationship

The cement-bond log (CBL) is a conventional and widely used cement quality evaluation technology for vertical wells. With the increase in horizontal wells around the world, the existing cement evaluation technologies are not appropriate. We have explored the possibilities of utilizing CBL in horizontal wells through investigating the effects of a noncentralized tool on CBL measurements. The parallel finite-difference numerical simulation method and experiments in calibration wells were adopted in the study. The numerical and experimental results matched very well, and indicated that the CBL amplitude decreases linearly with increasing tool eccentricity in a well with free pipe (i.e., a cased but uncemented well). For a standard pipe with a diameter of 5.5 in (139.7 mm) and a thickness of 7.72 mm, an eccentricity of [Formula: see text] (17% of the maximum eccentricity) could cause the CBL amplitude to be reduced by about 20%. The numerical simulations of CBL in wells with fluid channels in the cement showed that tool eccentralization could either increase or reduce the CBL amplitude relative to a centered tool, depending on the channel azimuth relative to eccentered direction. To explain this phenomenon, we investigated numerically the polarizations of casing waves in a well with free pipe and in a well with a fluid channel, and casing waves at higher frequencies in a well with free pipe. The relationship between the CBL amplitude and the percentage of cemented area for a borehole-centered tool was also studied. Our results provided some insights into understanding CBL measurements in horizontal wells.

Research of Flow Mechanism and Numerical Simulation on the Post-Prestressed Duct Grouting

2013 ◽  
Vol 405-408 ◽  
pp. 1567-1573
Author(s):  
Geng Xu ◽  
Ren Jun Yan ◽  
Chang Lian She ◽  
Lin Zhi Xu ◽  
Lin Xu ◽  
...  
Keyword(s):  
Numerical Simulation ◽  
Reference Value ◽  
Control Program ◽  
Simulation Method ◽  
Construction Process ◽  
Height Difference ◽  
Grouting Pressure ◽  
Parameters Analysis ◽  
Complex Construction ◽  
The Relationship

Post-prestressed duct grouting is a complex construction process and it is affected by many factors. Since there are no clear cognitive relations to the influencing factors of the grouting quality, it is hard to make the best control program during the construction. By the theoretical applicability and parameters analysis through the grouting process, this article used the numerical simulation method to analyze the grouting process and obtained the correspondence between the initial velocity, grouting pressure and grouting quality. To the height difference and bending in the duct, the relationship between volume and forming quality were analyzed, the results has reference value to the design of duct gas vent.

scholarly journals Influence of Backing Plate Support Conditions on Armor Ceramic Protection Efficiency

Materials ◽  
2020 ◽  
Vol 13 (15) ◽  
pp. 3427
Author(s):  
Bowen Zhang ◽  
Yangwei Wang ◽  
Shaofeng Du ◽  
Zhikun Yang ◽  
Huanwu Cheng ◽  
...  
Keyword(s):  
Numerical Simulation ◽  
Composite Ceramic ◽  
Simulation Method ◽  
Mechanical Support ◽  
Protection Efficiency ◽  
Positive Correlation ◽  
Backing Plate ◽  
The World ◽  
Support Conditions ◽  
The Relationship

The bilayer composite ceramic armor is widely used in the world, while the protection efficiency of the armor ceramic in it still confuses researchers. This study applied a numerical simulation method to produce a general equation that describes the relationship between the protection efficiency of the armor ceramic and the supporting conditions of the backing plate, thereby enhancing the current understanding of the composite ceramic armor. The results indicated that the protection efficiency of the armor ceramic can be divided into three parts: (1) the basic protection efficiency, (2) the increment efficiency caused by inertial support, and (3) the increment efficiency caused by mechanical support. The inertial support is related to the density and thickness of the backing plate, and the mechanical support is related to the elastic modulus and yield strength of the backing plate materials. The inertial support exhibited a positive correlation with the protection efficiency of the armor ceramic before it reached the Scr; after that, the protection efficiency of the armor ceramic would remain stable. In addition, the mechanical support showed a linear, positive correlation with the backing plate stress at ε0.

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