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Corresponding Author

Mahgoub, Mohamed

Subject Area

Mechanical Power Engineering

Article Type

Original Study

Abstract

The purpose of this work is to examine experimentally the validity of a two-dimensional analytical model proposed for prediction of the temperature distribution in a nuclear fuel rod in steady and transient conditions. Cooling around the fuel rod is considered non-uniform. The reactor fuel rod is replaced by an elecrically heated rod inserted in a cladding tube. The tube is cooled by natural convection in air at one side and by natural convection in water at the other side. Agreement between the theoretical and experimental temperature distribution of the tube surface prove the adequacy of the proposed analytical model.

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