Published 1980 | Version v1
Journal article Metadata-only

A method for solving multi-group diffusion equations

Creators

  • 1. Institutul de Reactori Nucleari Energetici, Pitesti (Romania)
  • 2. Bylgarska Akademiya na Naukite, Sofia. Inst. za Yadrena Izsledvaniya i Yadrena Energetika

Description

A method of the analytical solution of multigroup diffusion equations for media typical of fast neutron reactors is proposed. On the basis of this method a program for computing critical neutron physical parameters is developed. The computations after the analytical method are compared with the results obtained from the program employing the method of central finite differences. The advantages in accuracy and efficiency of the proposed approach are demonstrated

Additional details

Additional titles

Original title (Bulgarian)
Metod za reshavane na mnogogrupovite difuzionni uravneniya

Publishing Information

Journal Title
Yad. Energ.
Journal Volume
12
Series
Yad. Energ.
Journal Page Range
21-26
ISSN
0204-6989

INIS

Country of Publication
Bulgaria
Country of Input or Organization
Bulgaria
INIS RN
13659672
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
ACCURACY; COMPARATIVE EVALUATIONS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIFFUSION; FAST NEUTRONS; FINITE DIFFERENCE METHOD; MASURCA REACTOR; MULTIGROUP THEORY; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; PROGRAMMING; REACTOR PHYSICS
Descriptors DEC
BARYONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; FAST REACTORS; FERMIONS; HADRONS; ITERATIVE METHODS; NEUTRONS; NUCLEONS; NUMERICAL SOLUTION; PLUTONIUM REACTORS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; TRANSPORT THEORY; ZERO POWER REACTORS