In cooperation with the Iranian Nuclear Society

Analytical and Numerical Heat Transfer Analysis of Eccentric Fuel Pellets in a Fuel Element of Nuclear Reactor

Document Type : Research Paper

Authors

Abstract
A fuel element in nuclear reactors generally consists of fuel pellets, gaseous gap and cladding. Normally the pellets and cladding are coaxial. In this case; heat conduction equation in the fuel element is two dimensional, independent on angle (θ). Certainly elimination of gaseous gap in one direction (eccentricity of fuel pellets), will increase cladding and coolant temperature at the same direction. In this work, three dimensional analytical and numerical steady state heat transfer behavior in eccentric fuel element were studied to determine maximum temperature of fuel pellets, cladding, and coolant. Good agreement between analytical and numerical results was obtained. It is concluded that because of eccentricity of fuel element, melting of cladding and boiling in coolant will not occur.

Highlights

  1. 1.    M.M. EL-Wakil, Nuclear Heat Transport, 3rd Edition, The American Nuclear Society, USA, (1981).

 

  1. 2.    N.E. Todreas, M.S. Kazimi, Nuclear System II, Hemisphere Publishing Corporat­ion, (1990).

 

  1. 3.    E.R.G. Eckert and R.M. Drake, “Heat and Mass Transfer, 2nd Edition, McGraw-Hill Book Company,  New-York (1959).

 

  1. 4.     ح. امین‌فر و م. محمدپورفرد، ”آنالیز انتقال حرارت در میله سوخت راکتور هسته‌ای،“ مجله دانشکده فنی، دانشگاه تبریز، (زمستان 1384).                                                                          
  2. 5.    ح. امین‌فر و م. محمدپورفرد، ”بررسی عددی انتقال حرارت در کانال سوخت راکتور هسته‌ای،“ کنفرانس دینامیک شاره‌ها، دانشگاه شیراز (1384).                                                               

                                                           

  1. 6.    R.A. Churchil, J.W. Brown, “Complex variables and applications, fifth edition, McGraw-Hill Publication Company, New York (1990).

 

  1. 7.    M.S. Mayeri, S.A. Gandjalikhan Nassab, “A two dimentional thermohydro­dynamic analysys of journal bearing characteristics,” Iranian Journal of Science and Technology, No.3, p. 203 (2000).

 

  1. 8.    Fluent Package Manual, Version 6.0.12 (2002).

Keywords


  1. 1.    M.M. EL-Wakil, Nuclear Heat Transport, 3rd Edition, The American Nuclear Society, USA, (1981).

 

  1. 2.    N.E. Todreas, M.S. Kazimi, Nuclear System II, Hemisphere Publishing Corporat­ion, (1990).

 

  1. 3.    E.R.G. Eckert and R.M. Drake, “Heat and Mass Transfer, 2nd Edition, McGraw-Hill Book Company,  New-York (1959).

 

  1. 4.     ح. امین‌فر و م. محمدپورفرد، ”آنالیز انتقال حرارت در میله سوخت راکتور هسته‌ای،“ مجله دانشکده فنی، دانشگاه تبریز، (زمستان 1384).                                                                          
  2. 5.    ح. امین‌فر و م. محمدپورفرد، ”بررسی عددی انتقال حرارت در کانال سوخت راکتور هسته‌ای،“ کنفرانس دینامیک شاره‌ها، دانشگاه شیراز (1384).                                                               

                                                           

  1. 6.    R.A. Churchil, J.W. Brown, “Complex variables and applications, fifth edition, McGraw-Hill Publication Company, New York (1990).

 

  1. 7.    M.S. Mayeri, S.A. Gandjalikhan Nassab, “A two dimentional thermohydro­dynamic analysys of journal bearing characteristics,” Iranian Journal of Science and Technology, No.3, p. 203 (2000).

 

  1. 8.    Fluent Package Manual, Version 6.0.12 (2002).