June 12, 2005
June 12, 2005
June 15, 2005
10.902.1 - 10.902.16
Loss of Coolant Accident in a Natural Circulation Cooled Advanced Boiling Water Reactor
Phil Benavides, Jay Breitlow, Nick Lingler, Justin Thomas and Shripad T. Revankar
School of Nuclear Engineering Purdue University West Lafayette, IN 47907
Abstract This research involved undergraduate students to perform safety analyses of an advanced light water reactor designs and to observe flow phenomena that occur during LOCA. Both experimental and computational methods were developed. The design and construction of a small experimental facility capable of modeling specific aspects of phenomena during LOCA and the development of a thermal-hydraulics model for the facility were implemented. This facility was completed by first performing detailed scaling methods, which allowed for design and development of a physical experimental facility to produce and gather data, followed by modeling with RELAP5 thermalhydraulics codes to compare physical data to computationally generated data.
The U.S. Department of Energy (DOE) supports research in development of advanced nuclear reactors referred as Generation III and IV. It is expected that these advanced reactors have significant improvements over existing reactors in safety, economics, and proliferation resistance. The advanced light water reactor (ALWR) of focus in this study is the GE Simplified Boiling Water Reactor (SBWR), which has enhanced safety by implementing passive safety systems and simplifying the BWR design . The goal of this work was to introduce Purdue’s nuclear engineering students to the field of safety analysis of ALWR designs. This is done via exposure to the newly redesigned experimental facility to model phenomena during ALWR loss- of-coolant-accidents (LOCAs). Accompanying the facility, the thermal-hydraulic computational models have been developed using RELAP5. An existing blowdown facility which was used to simulate LOCA in a BWR was used in this study. The previous facility was small and had not been scaled to a BWR prototype, and was used as an educational tool that models local phenomena. In this study this facility was modified to model LOCA in an ALWR. The project objectives were: (1) to perform scaling analysis and successfully design and develop an experiment to model a LOCA in an ALWR; (3) to developed a RELAP5 model for the transient analysis and (4) to compare experimental data to the code results. The General Electric designed simplified boiling water reactor (SBWR) of 600 MWe  was used as the prototype reactor in this study.
Proceedings of the 2005 American Society for Engineering Education Annual Conference & Exposition Copyright © 2005, American Society for Engineering Education
Revankar, S. (2005, June), Loss Of Coolant Accident In A Natural Circulation Cooled Advanced Boiling Water Reactor Paper presented at 2005 Annual Conference, Portland, Oregon. 10.18260/1-2--15327
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