Published 1969 | Version v1
Miscellaneous Metadata-only

Numerical solution of multigroup diffusion equations

Creators

  • 1. IRCA, Energoinvest, Sarajevo (Yugoslavia)

Description

Full text: This paper describes the method used for writing two-dimensional multigroup codes for calculating neutron distribution in the reactor core. Differential diffusion equations are approximated by finite difference equations thus obtaining systems of linear equations which can be solved by iterative procedure. It was assumed that boundary conditions are of homogeneous type in the region where neutron flux is calculated. Different problems concerned with precision and convergence rate are analyzed in particular

Availability note (English)

Available in abstract form only, full text entered in this record

Abstract (Serbian)

Pun tekst: U radu je izlozena metoda koja je koriscena pri izradi dvodimenzionalnih visegrupnih programa za izracunavanje raspodele neutrona u reaktoru. Diferencijalne difuzione jednacine aproksimirane su jednacinama konacnih razlika cime je problem sveden na spregnute sisteme lineranih jednacina koji se resavaju iterativnim putem. Pretpostavljeno je da su, u granicama oblasti u kojoj se trazi neutronski fluks zadovoljeni granicni uslovi homogenog tipa. Posebno se analiziraju razliciti problemi u vezi sa tacnoscu rada i brzinom konvergencije. (author)

Additional details

Additional titles

Original title (Serbian)
Numericko resavanje grupnih difuzionih jednacina

Publishing Information

Publisher
Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
Imprint Place
Belgrade (Yugoslavia)
Imprint Pagination
1 p.

Conference

Title
ETAN 13. - Conference
Original Conference Title
Zbornik radova 13. Konferencija za ETAN
Dates
Jun 1969
Place
Subotica (Yugoslavia)

INIS

Country of Publication
Yugoslavia
Country of Input or Organization
Serbia
INIS RN
38088098
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BOUNDARY CONDITIONS; DIFFERENTIAL EQUATIONS; ITERATIVE METHODS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NUMERICAL SOLUTION; REACTOR CORES; SPATIAL DISTRIBUTION; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DISTRIBUTION; EQUATIONS; MATHEMATICAL SOLUTIONS; NEUTRON TRANSPORT THEORY; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; REACTOR COMPONENTS; TRANSPORT THEORY