Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations

Author:

Beuthe Thomas1,Vasić Aleksandar1,Azih Chukwudi2,Maqueo Pablo D. G.2

Affiliation:

1. Canadian Nuclear Laboratories , 286 Plant Road, Chalk River, ON K0J 1J0, Canada

2. Canadian Nuclear Laboratories , 286 Plant Road, Chalk River K0J 1J0, ON, Canada

Abstract

Abstract Advanced small modular reactors strive to improve reactor safety through increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes to cool the reactor under both normal and abnormal operating conditions. A heat pipe model has been added to the ARIANT thermalhydraulic code to enable reactor modeling and support the design and licensing of new reactors. Saturation fluid properties are a fundamental input to this model. Consequently, this article provides a comprehensive comparative overview of the best available sodium saturation property correlations developed over the past century. The results show most of the sodium property correlations needed to model a heat pipe are relatively well-defined and recommendations for their use can be provided.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference49 articles.

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