Published 1979
| Version v1
Miscellaneous
Multigroup flux and importance function synthesis for a two-dimensional reactor
Creators
Description
The iterative synthesis metod of neutron transport equation solution with the representation of the required solution by the sum of functions with divided variables is generalized to multidimensional spatial-energy problems. Described also is the method of obtaining and solving the equations for worth functions on the neutron field functionals. Obtained are the perturbation theory formulae for linear-fractional functionals of the neutron field. It is noted that the described method can be used for solving a multigroup three-dimensional problem without any principal changes
Additional details
Additional titles
- Original title (Russian)
- Синтез многогрупповых потоков и ценностей в двумерном реакторе
Publishing Information
- Imprint Title
- Nuclear reactor physics. No. 8
- Journal Page Range
- p. 54-63.
- Report number
- INIS-mf--6299
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 12585740
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CYLINDRICAL CONFIGURATION; FLUX DENSITY; FLUX SYNTHESIS; ITERATIVE METHODS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON IMPORTANCE FUNCTION; NUMERICAL SOLUTION; PERTURBATION THEORY; REACTOR CORES; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CONFIGURATION; RADIATION FLUX; REACTOR COMPONENTS
Optional Information
- Notes
- 7 refs. Imprint:Fizika yadernykh reaktorov. No. 8.;Sbornik statej.