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Analysis of heterogeneous reactors containing moderating fuel elements

Citation

Tesnière, André Jacques (1963) Analysis of heterogeneous reactors containing moderating fuel elements. Engineer's thesis, California Institute of Technology. http://resolver.caltech.edu/CaltechTHESIS:05182012-105801916

Abstract

The Feinberg-Galanin method for heterogeneous reactors is formulated by using a two-group model instead of an age kernel. This treatment is then extended to take into account secondary effects such as fast liasion and thermalization of neutrons inside a rod which may contain moderator. The use of single coefficient in a Feinberg-Galanin approach allows one to relate the source and sink strength of the fuel element to the thermal flux only. By defining a set of four coefficients it is possible to connect the strengths of thermal and fast neutron sources and sinks to both thermal and fast fluxes. A method of calculating these four coefficients α1, β1, α2 and β2 is presented.

The critical fuel mass of liasion electric cell reactor is calculated by using the four coefficient method. A value of approximately 0.77 kg is obtained, compared to a critical mass of 1.3 kg estimated from two-group homogeneous theory.

Item Type:Thesis (Engineer's thesis)
Subject Keywords:Mechanical Engineering
Degree Grantor:California Institute of Technology
Division:Engineering and Applied Science
Major Option:Mechanical Engineering
Thesis Availability:Public (worldwide access)
Research Advisor(s):
  • Estabrook, Frank B. (advisor)
  • Heindl, Clifford J. (advisor)
Thesis Committee:
  • Unknown, Unknown
Defense Date:1 January 1963
Record Number:CaltechTHESIS:05182012-105801916
Persistent URL:http://resolver.caltech.edu/CaltechTHESIS:05182012-105801916
Default Usage Policy:No commercial reproduction, distribution, display or performance rights in this work are provided.
ID Code:7047
Collection:CaltechTHESIS
Deposited By: Tony Diaz
Deposited On:18 May 2012 20:26
Last Modified:26 Dec 2012 04:43

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