Natural convection heat transfer within horizontal spent nuclear fuel assemblies
Abstract
Natural convection heat transfer is experimentally investigated in an enclosed horizontal rod bundle, which characterizes a spent nuclear fuel assembly during dry storage and/or transport conditions. The basic test section consists of a square array of sixtyfour stainless steel tubular heaters enclosed within a watercooled rectangular copper heat exchanger. The heaters are supplied with a uniform power generation per unit length while the surrounding enclosure is maintained at a uniform temperature. The test section resides within a vacuum/pressure chamber in order to subject the assembly to a range of pressure statepoints and various backfill gases. The objective of this experimental study is to obtain convection correlations which can be used in order to easily incorporate convective effects into analytical models of horizontal spent fuel systems, and also to investigate the physical nature of natural convection in enclosed horizontal rod bundles in general. The resulting data consist of: (1) measured temperatures within the assembly as a function of power, pressure, and backfill gas; (2) the relative radiative contribution for the range of observed temperatures; (3) correlations of convective Nusselt number and Rayleigh number for the rod bundle as a whole; and (4) correlations of convective Nusselt number as a function ofmore »
 Authors:
 Publication Date:
 Research Org.:
 Texas Univ., Austin, TX (United States)
 Sponsoring Org.:
 USDOE Office of Energy Research, Washington, DC (United States)
 OSTI Identifier:
 573364
 Report Number(s):
 DOE/OR/00033T746
ON: DE97053623; TRN: 98:008598
 DOE Contract Number:
 AC0576OR00033
 Resource Type:
 Technical Report
 Resource Relation:
 Other Information: TH: Thesis (Ph.D.); PBD: Dec 1995
 Country of Publication:
 United States
 Language:
 English
 Subject:
 05 NUCLEAR FUELS; NATURAL CONVECTION; SPENT FUEL ELEMENTS; DRY STORAGE; TRANSPORT; EXPERIMENTAL DATA; CORRELATIONS; TURBULENT FLOW
Citation Formats
Canaan, R.E.. Natural convection heat transfer within horizontal spent nuclear fuel assemblies. United States: N. p., 1995.
Web. doi:10.2172/573364.
Canaan, R.E.. Natural convection heat transfer within horizontal spent nuclear fuel assemblies. United States. doi:10.2172/573364.
Canaan, R.E.. 1995.
"Natural convection heat transfer within horizontal spent nuclear fuel assemblies". United States.
doi:10.2172/573364. https://www.osti.gov/servlets/purl/573364.
@article{osti_573364,
title = {Natural convection heat transfer within horizontal spent nuclear fuel assemblies},
author = {Canaan, R.E.},
abstractNote = {Natural convection heat transfer is experimentally investigated in an enclosed horizontal rod bundle, which characterizes a spent nuclear fuel assembly during dry storage and/or transport conditions. The basic test section consists of a square array of sixtyfour stainless steel tubular heaters enclosed within a watercooled rectangular copper heat exchanger. The heaters are supplied with a uniform power generation per unit length while the surrounding enclosure is maintained at a uniform temperature. The test section resides within a vacuum/pressure chamber in order to subject the assembly to a range of pressure statepoints and various backfill gases. The objective of this experimental study is to obtain convection correlations which can be used in order to easily incorporate convective effects into analytical models of horizontal spent fuel systems, and also to investigate the physical nature of natural convection in enclosed horizontal rod bundles in general. The resulting data consist of: (1) measured temperatures within the assembly as a function of power, pressure, and backfill gas; (2) the relative radiative contribution for the range of observed temperatures; (3) correlations of convective Nusselt number and Rayleigh number for the rod bundle as a whole; and (4) correlations of convective Nusselt number as a function of Rayleigh number for individual rods within the array.},
doi = {10.2172/573364},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1995,
month =
}

Natural convection heat transfer is experimentally investigated in an enclosed horizontal rod bundle, which characterizes a spentfuel assembly during transport and some dry storage scenarios. The objective of this experimental study is to obtain convection correlations that can be used to easily incorporate convective effects into analytical models of horizontal spentfuel systems and also to investigate the physical nature of natural convection in enclosed horizontal rod bundles in general. The resulting data consist of correlations of convective Nusselt number, which are defined in terms of the maximum and average assembly temperatures. The correlations have been corrected for radiation heat transfermore »

A numerical investigation of natural convection heat transfer within horizontal spentfuel assemblies
A numerical investigation of natural convection heat transfer is carried out for a single, horizontal, spentfuel assembly in an environment typical of spentfuel transportation systems as well as some dry storage/disposal scenarios. The objective is to predict computationally the convective heat transfer trends for horizontal spent fuel and to compare the results to data taken in a supporting experimental effort. The predicted data consist of thermal and flow fields throughout the assembly for a wide range of Rayleigh number, as well as numerically obtained Nusseltnumber data that are correlated as a function of Rayleigh number. Both laminar and turbulent approachesmore » 
A comparison of natural convection heat transfer for a staggered versus an aligned array of horizontal spent nuclear fuel rods within a rectangular enclosure
Natural convection heat transfer was experimentally investigated in a staggered array of heated cylinders, oriented horizontally within a rectangular isothermal enclosure. The test conditions were characteristic of a spentfuel assembly during transport or horizontal dry storage. The assembly was configured with a pitchtodiameter ratio of 1.33 and backfilled with pressurized helium or nitrogen. The backfill pressure was varied between 1 and 5 atm, while the assembly power was varied between 1 and 5 W per heater rod. The resulting data are presented in the form of NusseltRayleigh number correlations, where the Nusselt number has been corrected for thermal radiation usingmore » 
Steady natural convection heat transfer experiments in a horizontal annulus for the United States Spent Fuel Shipping Cask Technology Program. [LMFBR]
This experimental study deals with the measurement of the heat transfer across a horizontal annulus which is formed by an inner hexagonal cylinder and an outer concentric circular cylinder. The geometry simulates, in two dimensions, a liquid metal fast breeder reactor radioactive fuel subassembly inside a shipping container. This geometry is also similar to a radioactive fuel pin inside a horizontal reactor subassembly. The objective of the experiments is to measure the local and mean heat transfer at the surface of the inner hexagonal cylinder. 
Natural convection heat transfer for a staggered array of heated, horizontal cylinders within a rectangular enclosure
This thesis presents the results of an experimental investigation of natural convection heat transfer in a staggered array of heated cylinders, oriented horizontally within a rectangular enclosure. The main purpose of this research was to extend the knowledge of heat transfer within enclosed bundles of spent nuclear fuel rods sealed within a shipping or storage container. This research extends Canaan`s investigation of an aligned array of heated cylinders that thermally simulated a boiling water reactor (BWR) spent fuel assembly sealed within a shipping or storage cask. The results are presented in terms of piecewise NusseltRayleigh number correlations of the formmore »