Published July 2005 | Version v1
Journal article Metadata-only

Multigroup transport calculations of critical and fuel assemblies with taking into account the scattering anisotropy

Creators

  • 1. OIEhYaI - Sosny NAN Belarusi, Minsk (Russian Federation)

Description

A technique for calculation of reactor lattices by means of the transmission probabilities with taking into account the scattering anisotropy is generalized for the multigroup case. The errors of the calculated multiplication coefficients and energy release distributions do noe exceed practically the errors, of these values, obtained by the Monte Carlo method. The proposed method is most effective when determining the small difference effects

Abstract (Russian)

Методика расчета реакторных решеток посредством вероятностей прохождения с учетом анизотропии рассеяния обобщена на многогрупповой случай. Рассчитанные коэффициенты разложения и распределения энерговыделения по точности лишь немного уступают полученным методом Монте-Карло. Предложенный метод наиболее эффективен при определении небольших разностных эффектов

Additional details

Additional titles

Original title (Russian)
Многогрупповые расчеты критических и тепловыделяющих сборок с учетом анизотропии рассеяния

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
99
Journal Issue
1
Journal Page Range
p. 8-13
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
37070187
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ACCURACY; ANISOTROPY; COMPARATIVE EVALUATIONS; EFFICIENCY; ENERGY YIELD; FUEL ASSEMBLIES; MULTIGROUP THEORY; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; NOVOVORONEZH-5 REACTOR; PROBABILITY; REACTOR LATTICES; SCATTERING; SPATIAL DISTRIBUTION; ZERO POWER REACTORS
Descriptors DEC
DIMENSIONLESS NUMBERS; DISTRIBUTION; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT THEORY; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
8 refs., 3 figs., 4 tabs.