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research-article

PRESSURE MEASUREMENTS IN A WIRE-WRAPPED 61-PIN HEXAGONAL FUEL BUNDLE

[+] Author and Article Information
Rodolfo Vaghetto

Department of Nuclear Engineering, Texas A&M University
r.vaghetto@tamu.edu

Nolan Goth

Department of Nuclear Engineering, Texas A&M University
negcm7@tamu.edu

Philip Jones

Department of Nuclear Engineering, Texas A&M University
pgjones87@tamu.edu

Mason Childs

Department of Nuclear Engineering, Texas A&M University
masonchilds@tamu.edu

Saye Lee

Department of Nuclear Engineering, Texas A&M University
sayalee@tamu.edu

Duy Thien Nguyen

Department of Nuclear Engineering, Texas A&M University
thien.duy.ng@tamu.edu

Yassin A. Hassan

Department of Nuclear Engineering, Texas A&M University
y-hassan@tamu.edu

1Corresponding author.

ASME doi:10.1115/1.4038086 History: Received March 20, 2017; Revised August 27, 2017

Abstract

To achieve longer-life liquid-metal fast reactor cores, designers are considering to increase the wall gap of the wire-wrapped hexagonal fuel bundles to account for volumetric void swelling and radiation creep. A new wire-wrapped hexagonal test bundle has been constructed, with a wall gap larger than prior experiments, and experimental pressure drop data has been generated under laminar, transition, and turbulent flow regimes (corresponding to Re of 250 – 19,000), to complement the existing database of small wall gap experimental bundles. The comparison of the experimental data set with the predictions of four existing correlations (Baxi and Dalle Donne, Cheng and Todreas Detailed, Kirillov, and Rehme), showed general agreement between data and the selected correlations. However, the Cheng and Todreas Detailed correlation most accurately predicted the experimental trend, and the transition between flow regimes. The analysis of the experimental data also revealed that the larger wall gap size caused a lower bundle pressure drop due to the increased bypass flow area.

Copyright (c) 2017 by ASME
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