Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor-Reference-Cited by-同舟云学术

Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor

Published:2003-05-01 Issue:2 Volume:125 Page:233-238
ISSN:0094-9930
Container-title:Journal of Pressure Vessel Technology
language:en
Short-container-title:

Author:

Choi Seok Ki¹,Choi Il Kon¹,Nam Ho Yun¹,Choi Jong Hyeun¹,Choi Hoon Ki²

Affiliation:

1. Korea Atomic Energy Research Institute, KALIMER Technology Development Team, Taejon, 305-353, Korea

2. Changwon National University, Mechanical Engineering Department, Gyeongnam, 641-773, Korea

Abstract

An experimental study has been carried out to measure the pressure drop in a 271-pin fuel assembly of a liquid metal reactor. The rod pitch to rod diameter ratio P/D of the fuel assembly is 1.2 and the wire lead length to rod diameter ratio H/D is 24.84. Measurements are made for five different sections in a fuel assembly; inlet orifice, fuel assembly inlet, wire-wrapped fuel assembly, fuel assembly outlet and fuel assembly upper region. A series of water experiments have been conducted changing flow rate and water temperature. It is shown that the pressure drops in the inlet orifice and in the wire-wrapped fuel assembly are much larger than those in other regions. The measured pressure drop data in a wire-wrapped fuel assembly region is compared with the existing four correlations. It is shown that the correlation proposed by Cheng and Todreas fits best with the present experimental data among the four correlations considered.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Link

http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/125/2/233/5480941/233_1.pdf

Reference4 articles.

1. Novendstern, E. H. , 1972, “Turbulent Flow Pressure Drop Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System,” Nucl. Eng. Des., 22, pp. 19–27.

2. Rehme, K. , 1972, “Pressure Drop Correlations for Fuel Element Spacers,” Nucl. Technol., 17, pp. 15–23.

3. Engel, F. C., Markley, R. A., and Bishop, A. A., 1979, “Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles,” Nucl. Sci. Eng., 69, pp. 290–296.

4. Cheng, S. K., and Todreas, N. E., 1986, “Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters,” Nucl. Eng. Des., 92, pp. 227–251.

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