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Heat diffusion in cylindrical fuel elements of water cooled reactors

Technical Report:

Abstract

This report contains a theoretical study of heat diffusion in the cylindrical fuel elements of water reactors. After setting up appropriate boundary conditions on the temperature, the steady state Fourier equation is solved both for a flat and a tilted fission power source. It is shown that source tilting does not have an appreciable effect on the peak fuel temperature while the heat flux to the coolant suffers a circumferential variation of less than a half of that of the fission power. In the last section, the theory is extended to include the effect of a flat, time dependent fission power. The time dependent Fourier equation is solved by means of a Dini series of Bessel functions which is shown to be rapidly convergent. From this series is derived expressions for the fuel element transfer functions required in reactor servo-analysis. These have the form of a rapidly convergent series of time-lag terms. (author)
Authors:
Randles, J [1] 
  1. Technical Assessments and Services Division, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)
Publication Date:
Sep 15, 1961
Product Type:
Technical Report
Report Number:
AEEW-R-96
Resource Relation:
Other Information: Country of input: International Atomic Energy Agency (IAEA); 3 refs
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BESSEL FUNCTIONS; BOUNDARY CONDITIONS; COOLANTS; CYLINDRICAL CONFIGURATION; DIFFUSION; EQUATIONS; FISSION; FUEL ELEMENTS; HEAT; HEAT FLUX; NUCLEAR FUELS; STEADY-STATE CONDITIONS; TIME DEPENDENCE; TRANSFER FUNCTIONS; WATER; WATER COOLED REACTORS
OSTI ID:
20885188
Research Organizations:
United Kingdom Atomic Energy Authority, Reactor Group, Winfrith (United Kingdom)
Country of Origin:
United Kingdom
Language:
English
Other Identifying Numbers:
TRN: GB07A0238050659
Availability:
Available from INIS in electronic form; Also available from H.M. Stationery Office
Submitting Site:
GBN
Size:
36 pages
Announcement Date:
Jul 14, 2007

Technical Report:

Citation Formats

Randles, J. Heat diffusion in cylindrical fuel elements of water cooled reactors. United Kingdom: N. p., 1961. Web.
Randles, J. Heat diffusion in cylindrical fuel elements of water cooled reactors. United Kingdom.
Randles, J. 1961. "Heat diffusion in cylindrical fuel elements of water cooled reactors." United Kingdom.
@misc{etde_20885188,
title = {Heat diffusion in cylindrical fuel elements of water cooled reactors}
author = {Randles, J}
abstractNote = {This report contains a theoretical study of heat diffusion in the cylindrical fuel elements of water reactors. After setting up appropriate boundary conditions on the temperature, the steady state Fourier equation is solved both for a flat and a tilted fission power source. It is shown that source tilting does not have an appreciable effect on the peak fuel temperature while the heat flux to the coolant suffers a circumferential variation of less than a half of that of the fission power. In the last section, the theory is extended to include the effect of a flat, time dependent fission power. The time dependent Fourier equation is solved by means of a Dini series of Bessel functions which is shown to be rapidly convergent. From this series is derived expressions for the fuel element transfer functions required in reactor servo-analysis. These have the form of a rapidly convergent series of time-lag terms. (author)}
place = {United Kingdom}
year = {1961}
month = {Sep}
}