Eigen function Expansion Method for Solving One-Group Neutron Diffusion Equation

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Published: 2012-06-15
Keywords:
Eigen function Expansion Method, One-group Neutron Diffusion Equation, Neutron Flux Distribution, Vaccum boundary conditions, Square critical reactor

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A. Patra
Department of Mathematics National Institute of Technology, Rourkela-769008, India
S. Saha Ray
Department of Mathematics National Institute of Technology, Rourkela-769008, India
R. K. Bera
Heritage Institute of Technology Anandapur, East Kolkata Township, Kolkata-700107, India
B. B. Biswas
Reactor Control Division BARC, Trombay, Mumbai- 400085
S. Das

Abstract

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Vol. 16 No. 2 (2012): Table of Content

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This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.

Author Biographies

A. Patra, Department of Mathematics National Institute of Technology, Rourkela-769008, India

 

S. Saha Ray, Department of Mathematics National Institute of Technology, Rourkela-769008, India




How to Cite

1.
Eigen function Expansion Method for Solving One-Group Neutron Diffusion Equation. J. Int. Acad. Phys. Sci. [Internet]. 2012 Jun. 15 [cited 2026 Oct. 23];16(2):163-70. Available from: http://www.iaps.org.in/journal/index.php/journaliaps/article/view/403