Published June 2016 | Version v1
Journal article

Wire-Wrapped Fuel Pin Effect of Bundle Size on Temperature Distribution for Uniform Heat Flux

  • 1. Texas A and M Department of Nuclear Engineering: 3133 TAMU, College Station, TX 77843-3133 (United States)

Description

A common fuel arrangement for Sodium Fast Reactors (SFR) designs are hexagonal arrays of wire wrapped fuel pins. The helically wound wires redirect coolant to neighboring subchannels and increases mixing. The increased mixing of the coolant is beneficial to heat transfer from the fuel and prevents temperature peaking in hot channels that may occur. The purpose of this study is to observe the effect of bundle size on the temperature distribution of a coolant when a constant heat flux is implemented. Bundles of 19, 37, 61, and 91 pins were modeled. The wire-wrapping on fuel pins encourages interchannel mixing. With a constant heat flux the enhanced interchannel mixing has little observable effect. The temperature distributions of the subchannels has negligible dependence on radial or angular position. The temperature distribution additionally shows negligible dependence on the bundle size. The subchannel average temperatures further illustrate the homogeneity of the temperature across the bundles. Similarly oriented subchannels differ by less than two Kelvin. The temperature distribution within a single subchannel is fairly uniform, differing by about 15 K between the wall and the bulk flow, with the exception of two hot spots. The two hot spots, however, occur in two non-geometrically accurate locations, so little analysis can be performed. To better illustrate the effect of the enhanced mixing of the wire-wrapped fuel pins, a hot pin analysis should be performed to observe how the additional, non-uniform heat is dispersed. (authors)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
114
Journal Issue
1
Journal Page Range
p. 888-890
ISSN
0003-018X

Conference

Title
Annual Meeting of the American Nuclear Society
Dates
12-16 Jun 2016
Place
New Orleans, LA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
52032275
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANTS; DESIGN; FAST REACTORS; FUEL PINS; HEAT FLUX; HEAT TRANSFER; MIXING; TEMPERATURE DISTRIBUTION
Descriptors DEC
ENERGY TRANSFER; EPITHERMAL REACTORS; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
3 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States