State Nuclear Power Technology Corporation Research and Development Center

Beijing, China

State Nuclear Power Technology Corporation Research and Development Center

Beijing, China

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Xing M.,Nuclear Power Institute of China | Hu X.,State Nuclear Power Technology Corporation Research and Development Center | Chen Y.,Nuclear Power Institute of China | Li L.,Xi'an Jiaotong University | Ma W.,KTH Royal Institute of Technology
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2013

OECD/NEA ROSA/LSTF project tests are performed on the Large Scale Test Facility (LSTF). LSTF is a full-height, fullpressure and 1/48 volumetrically-scaled two-loop system which aims to simulate Japanese Tsuruga-2 Westinghouse-type 4-loop PWR. ROSA-V Test 6-1 simulates a pressure vessel (PV) upper-head small break loss-of-coolant accident (SBLOCA) with a break size equivalent to 1.9% of the volumetrically scaled cross-sectional area of the reference PWR cold leg. By building a TRACE calculation model of LSTF and PV upper-head, the paper dedicated to assess the effect of different modeling options and parameters on simulating thermal hydraulic behaviors of TRACE code. The results show that TRACE code well reproduce the physical phenomena involved in this type of SBLOCA scenarios. Almost all the events in the experiment are well predicted by the model based on TRACE code. In addition, the sensitivity of different models and parameters are investigated. For example, the code slightly overestimated the break mass flow from upper head which could affect the accuracy of the results significantly. The rising of core exit temperature (CET) is significantly influenced by the bypass flow area between downcomer and hot leg. Copyright © 2013 by ASME.


Zhang J.,State Nuclear Power Technology Corporation Research and Development Center | Bo H.,Tsinghua University | Hu W.,China Power Engineering Consulting Group Corporation
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2013

A typical bend pipe in the fuel transporting and refueling system in the HTR is studied. The helium three-dimension flow field in the bend pipe is simulated and the graphite dust particle movement and impingement in the helium flow field are researched by numerical simulation. The trajectories of graphite particles with different diameters and different initial positions are simulated. The position and probability of the graphite particle collision is studied by the numerical simulation on the particle movement. Copyright © 2013 by ASME.


Zhang J.-Y.,Tsinghua University | Zhang J.-Y.,State Nuclear Power Technology Corporation Research and Development Center | Bo H.-L.,Tsinghua University
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2012

According to the force on the droplet and droplet physical properties, the droplet physical state was described and the three-dimension single droplet model was established based on the physical description and mechanism research on the droplet movement. The droplet model was applied to simulate the droplet movement in the wave-type vane steam separator, in which the steam fluid field was numerical simulated and movements of the droplets were simulated by calculation procedure. The droplet behavior mechanism in the steam flow field in the wave-type vane was explained.


Han Y.,State Nuclear Power Technology Corporation Research and Development Center | Shen X.,North China Electrical Power University | Guo J.,North China Electrical Power University
Applied Mechanics and Materials | Year: 2013

Energy is the power sources of economic growth. But, its consumption can also cause the environmental pollution. In this paper, we introduce Beijing Energy policy Simulation System, which is a simulate software to help researchers with studying energy, economy and environment. This system collects historical data throughout the years, and its applications mainly contain Energy Index Data Acquisition Subsystem (EIDAS), Energy Index Comparison Analysis Subsystem (EICAS), Energy Factor Analysis Subsystem (EFAS) and Energy Control Simulation Subsystem (ECSS). This paper displays the index system of Beijing Energy policy Simulation System, which is the precondition and foundation of the research. The main purpose of this paper is to introduce Feedback control thought into Energy policy Simulation System. © (2013) Trans Tech Publications, Switzerland.


Du W.-F.,CAS Institute of Mechanics | Du W.-F.,State Nuclear Power Technology Corporation Research and Development Center | Zhao J.-F.,CAS Institute of Mechanics | Li K.,CAS Institute of Mechanics
Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics | Year: 2014

Flashing liquid jets of distilled water through a long, straight stainless steel capillary with an inner diameter of 0.226 mm and a length of 16.5 mm into a vacuum environment are studied experimentally. Three kinds of jet patterns are observed. For the case of low initial temperature which is lower than the saturated temperature corresponding with the backpressure inside the vacuum chamber, no evaporation occurs, and then the flow of the liquid jet from the nozzle exit remains intact and follows a straight path. On the other hand, if the initial temperature is higher than the saturated temperature corresponding with the backpressure, evaporation will take place, which results in a visible irregular evaporation waves around the liquid core and then a shattering jet. On further decreasing the backpressure, the liquid jet shatters giving rise to a cloud of droplets with a spray angle usually bigger than 90 degree, indicating a large number of nucleation sites and rapid bubble growth. It is also shown that there is flow choking behavior as the flow rate becomes constant and insensitive to pressure reduction below some backpressure threshold, and thus, the flow exhibits a strong compressible characteristic.


Tian C.L.,State Nuclear Power Technology Corporation Research and Development Center | Yang L.,State Nuclear Power Technology Corporation Research and Development Center | Zhao R.C.,State Nuclear Power Technology Corporation Research and Development Center
Applied Mechanics and Materials | Year: 2014

In order to obtain frequencies and modal shapes of a nuclear containment vessel, the computational analyses have been carried out through free structure finite element analysis software. The finite element model of the vessel is built with shell element and solved by the type of the dynamics frequency solver. Results show that mainly deformation area is on the vessel's cylindrical shell and the maximum displacements occur at its center. Compared with the design validation values, the frequencies obtained are a little lower. It may be because that the model built here is a completely vessel shell without any hatches or attachments. It is provided that a reliable method of computational structural analyses for the nuclear containment without commercial software cost. © (2014) Trans Tech Publications, Switzerland.


Wang H.,State Nuclear Power Technology Corporation Research and Development Center | Zhang Z.-Y.,Shanghai University of Finance and Economics | Yang Y.-M.,Fudan University | Zhang H.-S.,Fudan University
Journal of Hydrodynamics | Year: 2011

In the inviscid and incompressible fluid flow regime, surface tension effects on the behavior of two initially spherical bubbles with same size rising axisymmetrically in an infinite and initially stationary liquid are investigated numerically with the VOF method. The numerical experiments are performed for two bubbles with two different bubble distances. The ratio of gas density to liquid density is 0.001, which is close to the case of air bubbles rising in water. In the case of Dis = 2.5, where Dis is defined as the ratio of the distance between the bubble centroids to the radius of the bubble, it is found from numerical experiments that there exist four critical Weber numbers We1, We2, We3 and We4, which are in between 10 and 100, 3 and 4, 1.5 and 1.8, and 0.2 and 0.3, respectively. In the case of Dis = 2.3, similar phenomena also appear but the corresponding four critical Weber numbers are lower than those in the case of Dis = 2.5. The mechanism of the above phenomena is analyzed theoretically and numerically. © 2011 Publishing House for Journal of Hydrodynamics.


Tian C.L.,State Nuclear Power Technology Corporation Research and Development Center | Shan Z.,State Nuclear Power Technology Corporation Research and Development Center | Han L.Y.,State Nuclear Power Technology Corporation Research and Development Center
Applied Mechanics and Materials | Year: 2014

A numerical simulation model of heat flux sensors embedded in a flat plate is established. Each sensor has four thermal couples and is inserted into the specified hole. The problem is defined as a steady heat conduction problem with specified boundary conditions and solved by the finite element method. The results of the simulation case demonstrate that the maximum heat flux appears near the sensor shell. The average heat flux of the plate is much smaller than the maximum. Due to exiting of the contact heat resistance, the temperature of the sensor is much lower than that of the plate at horizontal surface. The maximum temperature difference appears on the bottom shell of the sensor. The maximum temperature difference between the simulation results and the experimental data at test points is 1.5 K. The model is verified and could be accepted for the further errors analysis. © (2014) Trans Tech Publications, Switzerland.


Tian C.L.,State Nuclear Power Technology Corporation Research and Development Center | Zhou S.,State Nuclear Power Technology Corporation Research and Development Center | Han L.Y.,State Nuclear Power Technology Corporation Research and Development Center
Applied Mechanics and Materials | Year: 2014

A rectangular vessel has two contact surfaces with different materials, iron and copper. In order to investigate thermo-structural characteristics of the vessel, the structural model is developed. The structural analysis is coupled with the thermal condition. The numerical simulation model with hex eight-node thermally coupled brick elements is established and solved by finite element method. The results show that the maximum stress with 112.5 MPa is distributed on the contact surface between the different materials. Because of the different materials' expansions, there is stress concentration on the contact surface. The maximum displacement is 0.27 mm, almost the same at different pressure loads. The maximum stress increased to about 300 MPa as the temperature increase. The structural response caused by thermal expansion is important for the vessel design. © (2014) Trans Tech Publications, Switzerland.

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