Abstract
A combination of multigroup method and P{sub 3} approximation of spherical harmonics method was chosen for calculating space-energy distribution of thermal neutron flux in elementary reactor cell. Application of these methods reduced solution of complicated transport equation to the problem of solving an inhomogeneous system of six ordinary firs-order differential equations. A procedure is proposed which avoids numerical solution and enables analytical solution when applying certain approximations. Based on this approach, computer codes were written for ZUSE-Z-23 computer: SIGMA code for calculating group constants for a given material; MULTI code which uses results of SIGMA code as input and calculates spatial ana energy distribution of thermal neutron flux in a reactor cell. Calculations of thermal neutron spectra for a number of reactor cells were compared to results available from literature. Agreement was satisfactory in all the cases, which proved the correctness of the applied method. Some possibilities for improving the precision and acceleration of the calculation process were found during calculation. (author)
Matausek, M V
[1]
- Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)
Citation Formats
Matausek, M V.
Determining space-energy distribution of thermal neutrons in heterogeneous cylindrically symmetric reactor cell, Master Thesis; Odredjivanje prostorno energetske raspodele fluksa termalnih neutrona u heterogenoj cilindricno simetricnoj reaktorskoj celiji, Magistarski rad.
Serbia: N. p.,
1966.
Web.
Matausek, M V.
Determining space-energy distribution of thermal neutrons in heterogeneous cylindrically symmetric reactor cell, Master Thesis; Odredjivanje prostorno energetske raspodele fluksa termalnih neutrona u heterogenoj cilindricno simetricnoj reaktorskoj celiji, Magistarski rad.
Serbia.
Matausek, M V.
1966.
"Determining space-energy distribution of thermal neutrons in heterogeneous cylindrically symmetric reactor cell, Master Thesis; Odredjivanje prostorno energetske raspodele fluksa termalnih neutrona u heterogenoj cilindricno simetricnoj reaktorskoj celiji, Magistarski rad."
Serbia.
@misc{etde_21049588,
title = {Determining space-energy distribution of thermal neutrons in heterogeneous cylindrically symmetric reactor cell, Master Thesis; Odredjivanje prostorno energetske raspodele fluksa termalnih neutrona u heterogenoj cilindricno simetricnoj reaktorskoj celiji, Magistarski rad}
author = {Matausek, M V}
abstractNote = {A combination of multigroup method and P{sub 3} approximation of spherical harmonics method was chosen for calculating space-energy distribution of thermal neutron flux in elementary reactor cell. Application of these methods reduced solution of complicated transport equation to the problem of solving an inhomogeneous system of six ordinary firs-order differential equations. A procedure is proposed which avoids numerical solution and enables analytical solution when applying certain approximations. Based on this approach, computer codes were written for ZUSE-Z-23 computer: SIGMA code for calculating group constants for a given material; MULTI code which uses results of SIGMA code as input and calculates spatial ana energy distribution of thermal neutron flux in a reactor cell. Calculations of thermal neutron spectra for a number of reactor cells were compared to results available from literature. Agreement was satisfactory in all the cases, which proved the correctness of the applied method. Some possibilities for improving the precision and acceleration of the calculation process were found during calculation. (author)}
place = {Serbia}
year = {1966}
month = {Jun}
}
title = {Determining space-energy distribution of thermal neutrons in heterogeneous cylindrically symmetric reactor cell, Master Thesis; Odredjivanje prostorno energetske raspodele fluksa termalnih neutrona u heterogenoj cilindricno simetricnoj reaktorskoj celiji, Magistarski rad}
author = {Matausek, M V}
abstractNote = {A combination of multigroup method and P{sub 3} approximation of spherical harmonics method was chosen for calculating space-energy distribution of thermal neutron flux in elementary reactor cell. Application of these methods reduced solution of complicated transport equation to the problem of solving an inhomogeneous system of six ordinary firs-order differential equations. A procedure is proposed which avoids numerical solution and enables analytical solution when applying certain approximations. Based on this approach, computer codes were written for ZUSE-Z-23 computer: SIGMA code for calculating group constants for a given material; MULTI code which uses results of SIGMA code as input and calculates spatial ana energy distribution of thermal neutron flux in a reactor cell. Calculations of thermal neutron spectra for a number of reactor cells were compared to results available from literature. Agreement was satisfactory in all the cases, which proved the correctness of the applied method. Some possibilities for improving the precision and acceleration of the calculation process were found during calculation. (author)}
place = {Serbia}
year = {1966}
month = {Jun}
}