scholarly journals Multi-phase model development to assess RCIC system capabilities under severe accident conditions

2017 ◽  
Author(s):  
Karen Vierow Kirkland ◽  
Kyle Ross ◽  
Bradley Beeny ◽  
Nicholas Luthman ◽  
Zachary Strater
2017 ◽  
Author(s):  
Heeseok Koo ◽  
Alexander Brown ◽  
Tyler Voskuilen ◽  
Flint Pierce

Author(s):  
Steven W. Kirkpatrick

Significant research has been conducted over the past few years to develop improved railroad tank cars that maintain tank integrity for more severe accident conditions than current equipment. The approach taken in performing this research is to define critical collision conditions, evaluate the behavior of current design equipment in these scenarios, and develop alternative strategies for increasing the puncture resistance. The evaluations are being performed with finite element models of the tank cars incorporating a high level of detail. Both laboratory scale and full-scale impact tests were performed to validate the modeling and ultimately compare the effectiveness of current and alternative equipment designs. This paper describes the development of the detailed finite element model of the tank car and the use of the model for impact and puncture analyses. The validation of the model using the results of the full-scale impact tests is presented. The subsequent application of the model to assess the puncture resistance of existing tank car designs is discussed.


2014 ◽  
Vol 2014 ◽  
pp. 1-9 ◽  
Author(s):  
Ayah Elshahat ◽  
Timothy Abram ◽  
Judith Hohorst ◽  
Chris Allison

Great interest is given now to advanced nuclear reactors especially those using passive safety components. The Westinghouse AP1000 Advanced Passive pressurized water reactor (PWR) is an 1117 MWe PWR designed to achieve a high safety and performance record. The AP1000 safety system uses natural driving forces, such as pressurized gas, gravity flow, natural circulation flow, and convection. In this paper, the safety performance of the AP1000 during a small break loss of coolant accident (SBLOCA) is investigated. This was done by modelling the AP1000 and the passive safety systems employed using RELAP/SCDAPSIM code. RELAP/SCDAPSIM is designed to describe the overall reactor coolant system (RCS) thermal hydraulic response and core behaviour under normal operating conditions or under design basis or severe accident conditions. Passive safety components in the AP1000 showed a clear improvement in accident mitigation. It was found that RELAP/SCDAPSIM is capable of modelling a LOCA in an AP1000 and it enables the investigation of each safety system component response separately during the accident. The model is also capable of simulating natural circulation and other relevant phenomena. The results of the model were compared to that of the NOTRUMP code and found to be in a good agreement.


2012 ◽  
Vol 246 ◽  
pp. 157-162 ◽  
Author(s):  
Emilie Beuzet ◽  
Jean-Sylvestre Lamy ◽  
Hadrien Perron ◽  
Eric Simoni ◽  
Gérard Ducros

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