Abstract
Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.
Strugar, P V
[1]
- Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)
Citation Formats
Strugar, P V.
Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora.
Serbia: N. p.,
1968.
Web.
Strugar, P V.
Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora.
Serbia.
Strugar, P V.
1968.
"Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora."
Serbia.
@misc{etde_20826431,
title = {Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora}
author = {Strugar, P V}
abstractNote = {Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.}
place = {Serbia}
year = {1968}
month = {Jul}
}
title = {Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora}
author = {Strugar, P V}
abstractNote = {Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.}
place = {Serbia}
year = {1968}
month = {Jul}
}