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Loss Of Coolant Accident In A Natural Circulation Cooled Advanced Boiling Water Reactor

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Conference

2005 Annual Conference

Location

Portland, Oregon

Publication Date

June 12, 2005

Start Date

June 12, 2005

End Date

June 15, 2005

ISSN

2153-5965

Conference Session

Topics of Interest-Nuclear Engineering

Page Count

16

Page Numbers

10.902.1 - 10.902.16

Permanent URL

https://peer.asee.org/15327

Download Count

45

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Paper Authors

author page

Shripad Revankar

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Abstract
NOTE: The first page of text has been automatically extracted and included below in lieu of an abstract

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.

1. Introduction

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 [1]. 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 [1] 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. https://peer.asee.org/15327

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