Nuclear reactor fuel assemblies are mainly composed of cylinders bundle(CB),calculating the dynamics charac-teristics of CB under axial flow can lay a founda-tion for predicting fretting wear and vibration fatigue.
In reactor,FIV study is still a hot topic Nowadays.However,many experts keep a viewpoint of the combination between theorum model and semi-emprical equation for the FIV mechanism study.Many papers,including monography...In reactor,FIV study is still a hot topic Nowadays.However,many experts keep a viewpoint of the combination between theorum model and semi-emprical equation for the FIV mechanism study.Many papers,including monographys about FIV study,already appeared.A preliminary idea is that FIV mechanism is divided into turbulent excitation,vortex shedding,fluidelastic instability and acousitc reasonance,etc.[1−4].According to the flow form of fluid in reactor,the vibration mechanism can be thought vibration induced by transverse flow,axial flow,leakage flow.In previous reactors designed in home and abroad,there have been many accidents caused by FIV.Tsinghua Unversity have reviewed the FIV mechanism in detail[5;6],who are from China Nuclear Power Institute,sumerized FIV problem in nuclear power plant,including conveying flow pipe FIV and numerical simulation method.These work mainly study FIV phenomena and method,but little attetion to FIV effect and experiment measurement techniques.展开更多
1.MCNPX target physics computation The purpose of physical check is mainly to check whether the parameters in the XADS reports[1]are reasonable,to give the results and analysis and get the energy distribution of the t...1.MCNPX target physics computation The purpose of physical check is mainly to check whether the parameters in the XADS reports[1]are reasonable,to give the results and analysis and get the energy distribution of the target window and target zone,so as to provide heat source for thermal engineering and structure.According to the reference,the proton beam energy is 600 MeV and the beam current is 6 mA.The footprint of the beam has a circular shape with the radius of 8 cm and the beam intensity following an elliptical radical distribution is given.The thickness of target window and beam tube is 3 mm,and the thickness of structural material is 5 mm,and the spherical radius of target window is 10 cm.Heavy metal material is LBE.All physical check calculations are accomplished by MCNPX2.7.0.The final physical results are showed in Table 1.展开更多
Brief description of research in nuclear engineering,the safety of reactor design is very important.The structure inside the reactor and coolant constitute a complex fluid solid coupling system,so the flow induced vib...Brief description of research in nuclear engineering,the safety of reactor design is very important.The structure inside the reactor and coolant constitute a complex fluid solid coupling system,so the flow induced vibration(FIV)is inevitable.In this paper,the specific influence of FIV,such as vibration amplitude,frequency,structural stablity,nonlinear dynamic characteristics,etc,and analysis and computational method for the influence of structural vibration damage are studied and discussed.In the end,two methods of measuring the FIV and some strategies for vibration suppression design in the future development are summed up.The cladding of fuel rod is regard as the first safety barrier in nuclear reactor,and it is important to do its life analysis and calculation.展开更多
文摘Nuclear reactor fuel assemblies are mainly composed of cylinders bundle(CB),calculating the dynamics charac-teristics of CB under axial flow can lay a founda-tion for predicting fretting wear and vibration fatigue.
文摘In reactor,FIV study is still a hot topic Nowadays.However,many experts keep a viewpoint of the combination between theorum model and semi-emprical equation for the FIV mechanism study.Many papers,including monographys about FIV study,already appeared.A preliminary idea is that FIV mechanism is divided into turbulent excitation,vortex shedding,fluidelastic instability and acousitc reasonance,etc.[1−4].According to the flow form of fluid in reactor,the vibration mechanism can be thought vibration induced by transverse flow,axial flow,leakage flow.In previous reactors designed in home and abroad,there have been many accidents caused by FIV.Tsinghua Unversity have reviewed the FIV mechanism in detail[5;6],who are from China Nuclear Power Institute,sumerized FIV problem in nuclear power plant,including conveying flow pipe FIV and numerical simulation method.These work mainly study FIV phenomena and method,but little attetion to FIV effect and experiment measurement techniques.
文摘1.MCNPX target physics computation The purpose of physical check is mainly to check whether the parameters in the XADS reports[1]are reasonable,to give the results and analysis and get the energy distribution of the target window and target zone,so as to provide heat source for thermal engineering and structure.According to the reference,the proton beam energy is 600 MeV and the beam current is 6 mA.The footprint of the beam has a circular shape with the radius of 8 cm and the beam intensity following an elliptical radical distribution is given.The thickness of target window and beam tube is 3 mm,and the thickness of structural material is 5 mm,and the spherical radius of target window is 10 cm.Heavy metal material is LBE.All physical check calculations are accomplished by MCNPX2.7.0.The final physical results are showed in Table 1.
文摘Brief description of research in nuclear engineering,the safety of reactor design is very important.The structure inside the reactor and coolant constitute a complex fluid solid coupling system,so the flow induced vibration(FIV)is inevitable.In this paper,the specific influence of FIV,such as vibration amplitude,frequency,structural stablity,nonlinear dynamic characteristics,etc,and analysis and computational method for the influence of structural vibration damage are studied and discussed.In the end,two methods of measuring the FIV and some strategies for vibration suppression design in the future development are summed up.The cladding of fuel rod is regard as the first safety barrier in nuclear reactor,and it is important to do its life analysis and calculation.
