scholarly journals Seismic stress analysis of feeder lines to LOFT primary coolant pump motors

1978 ◽  
Author(s):  
C.J. Kuehster
Keyword(s):  
Stress Analysis ◽  
Primary Coolant ◽  
Coolant Pump ◽  
Seismic Stress

Stress analysis of shrink fitting process of ultra-thin reactor coolant pump rotor-can

2021 ◽  
Vol 162 ◽  
pp. 108492
Author(s):  
Yan Cui ◽  
Liwen Zhang ◽  
Chi Zhang ◽  
Ruiqin Li ◽  
Fei Li
Keyword(s):  
Stress Analysis ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Pump Rotor ◽  
Shrink Fitting

Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant

2017 ◽  
Author(s):  
Jian Zhang ◽  
Yongde Zuo ◽  
Xingjiang Chen ◽  
Qinghong Zhang
Keyword(s):  
Kinetic Energy ◽  
Failure Analysis ◽  
Stress Analysis ◽  
Ductile Failure ◽  
High Energy ◽  
Theory Of Elasticity ◽  
The Other ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Pump Rotor

The flywheels on reactor coolant pump motors provide inertia to ensure a slow decrease in coolant flow in order to prevent fuel damage as a result of a loss of power to the pump motors. During operation at normal speed, a flywheel has sufficient kinetic energy to produce high-energy missiles and excessive vibration of the reactor coolant pump assembly if the flywheel failed. Overspeed of the pump rotor assembly during a transient increases both the potential for failure and the kinetic energy of the flywheel. The safety consequences could be significant because of possible damage to the reactor coolant system, the containment, or other equipment or systems important to safety. Usually, the design of connection between flywheel and pump rotor has two types, one is keyway, and the other is rotor shrink fitting. This paper has done the research on the analysis of the integrity of flywheel in design rules and guidelines, such as NUREG, RG and NB, which have given the allowable stress limits but not given the potential for failures types and the stress verification type. So the stress verification of the flywheel is different in different technicals and structures. Some papers also have different analysis methods in China. This paper considers the failures mode of flywheel, using the analytical method in THEORY OF ELASTICITY and Tresca criteria to give the method of the stress analysis of flywheel. Next, this paper pays attention on the analysis of the flywheel integrity about two connection types, and gives the other requirements of integrity. Such as stress analysis, fatigue analysis, ductile failure analysis, non-ductile failure analysis, crack propagation analysis etc.

Reactor Coolant Pump Flywheel Overspeed Evaluation

1974 ◽  
Vol 96 (4) ◽  
pp. 279-285 ◽  
Author(s):  
P. C. Riccardella ◽  
W. H. Bamford
Keyword(s):  
Fracture Mechanics ◽  
Ductile Failure ◽  
Light Water Reactor ◽  
Scale Model ◽  
Intensity Factors ◽  
Test Program ◽  
Primary Coolant ◽  
Coolant Pump ◽  
Reactor Primary Coolant ◽  
Experimental Effort

The overspeed capability of the large steel flywheels used on light water reactor primary coolant pumps has been evaluated through a combined analytical and experimental effort. Limiting speeds of the prototype flywheel design were calculated for the ductile failure mode using the principles of Section III of the ASME Boiler and Pressure Vessel Code, and for the brittle fracture mode using a fracture mechanics approach in which stress intensity factors were determined from finite element computer analysis. The accuracy of the analytical approach was verified by a scale model test program which demonstrates excellent agreement between experiment and analysis. The results of the evaluation are presented in this paper, and they illustrate the kinds of things which can be accomplished through application of modern fracture mechanics technology, including plasticity considerations, to the solution of hardware problems of real engineering interest.

Thermal Analysis of the FSP-1 Experiment in the Advanced Test Reactor

2016 ◽  
Author(s):  
Grant L. Hawkes ◽  
Nicolas E. Woolstenhulme
Keyword(s):  
Thermal Analysis ◽  
Flow Instability ◽  
National Laboratory ◽  
Safety Evaluation ◽  
Thermal Safety ◽  
Primary Coolant ◽  
Coolant Pump ◽  
Safety Margins ◽  
Enriched Uranium ◽  
Test Reactor

The U.S. High Performance Research Reactor Conversions fuel development team is focused on developing and qualifying the uranium-molybdenum (U-Mo) alloy monolithic fuel to support conversion of domestic research reactors to low enriched uranium. Several previous irradiations have demonstrated the favorable behavior of the monolithic fuel. The Full Scale Plate 1 (FSP-1) fuel plate experiment will be irradiated in the northeast (NE) flux trap of the Advanced Test Reactor (ATR). This fueled experiment contains six aluminum-clad fuel plates consisting of monolithic U-Mo fuel meat. Three different types of fuel plates with matching pairs for a total of six plates were analyzed. These three types of plates are: full burn, intermediate power, and thick meat. A thermal analysis has been performed on the FSP-1 experiment to be irradiated in the ATR at the Idaho National Laboratory (INL). A thermal safety evaluation was performed to demonstrate that the FSP-1 irradiation experiment complies with the thermal-hydraulic safety requirements of the ATR Safety Analysis Report (SAR). The ATR SAR requires that minimum safety margins to critical heat flux and flow instability be met in the case of a loss of commercial power with primary coolant pump coast-down to emergency flow. The thermal safety evaluation was performed at 26 MW NE lobe power to encompass the expected range of operating power during a standard cycle. Additional safety evaluations of reactivity insertion events, loss of coolant event, and free convection cooling in the reactor and in the canal are used to determine the response of the experiment to these events and conditions. This paper reports and shows that each safety evaluation complies with each safety requirement of the ATR SAR.

Flow Transient in Primary Coolant System During Reactor Coolant Pump Start-Up Period

2013 ◽  
Author(s):  
Hong Gao ◽  
Feng Gao ◽  
Xianchao Zhao ◽  
Jie Chen ◽  
Xuewu Cao
Keyword(s):  
Primary Coolant ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Start Up ◽  
Coolant System
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