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On a boundary-value problem posed by cancer therapy with neutron beams

Published online by Cambridge University Press:  17 February 2009

Nassar H. S. Haidar
Nassar H. S. Haidar
Affiliation:
Departments of Mathematics and Physics, American University of Beirut, Beirut, Lebanon, email: nhaidar@aub.edu.lb
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Abstract

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This paper contains a detailed formulation of advanced tumor therapy with neutron beams as a mixed boundary initial value problem for multigroup neutron diffusion in a composite 3D multiregional system. By applying a vector-matrix composite region finite-integral transformation we derive the principal operational solution to this problem as the group-regional neutron flux distribution inside the tumor 3D subregions. The principal solution is then converted into expressions of various order approximation, which may be directly programmed on a computer.

Type
Research Article
Information
The ANZIAM Journal , Volume 39 , Issue 1 , July 1997 , pp. 46 - 60
Copyright
Copyright © Australian Mathematical Society 1997

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