Published June 2005 | Version v1
Journal article Metadata-only

Calculation of the high burnup of nuclear fuel in lattices with a controlled neutron spectra

Creators

  • 1. MIFI, Moscow (Russian Federation)

Description

The paper is devoted to a technique for calculation of fuel burnup in multiplicating media with a controlled neutron spectra. Using the small perturbation method permits to supplement the set of equations of variation of the fuel nuclide composition by the equation of the spectrum hardness variation during the fuel burnup under condition of conservation of a given criticality. An algorithm is developed for determining the multiplicating properties of the system with controlled neutron spectra and its time characteristics in the process of fuel burnup

Abstract (Russian)

Работа посвящена описанию методики расчета выгорания ядерного топлива в размножающих средах с регулируемым спектром нейтронов. Применение метода малых возмущений позволило дополнить систему уравнений изменения нуклидного состава топлива уравнением изменения жесткости спектра в процессе выгорания топлива при сохранении заданной критичности. Был разработан алгоритм определения размножающих свойств системы с регулирумым спектром нейтронов и ее характеристик в процессе выгорания топлива

Additional details

Additional titles

Original title (Russian)
Расчет глубокого выгорания ядерного топлива в решетках с регулируемым спектром нейтронов

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
98
Journal Issue
6
Journal Page Range
p. 429-435
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
37070182
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALGORITHMS; BURNUP; COMPUTER CALCULATIONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE RATIO; MULTIPLICATION FACTORS; NEUTRON SPECTRA; NUCLEAR FUELS; REACTOR LATTICES; TIME DEPENDENCE
Descriptors DEC
DIMENSIONLESS NUMBERS; ENERGY SOURCES; FUELS; MATERIALS; MATHEMATICAL LOGIC; REACTOR MATERIALS; REACTORS; SPECTRA

Optional Information

Notes
7 refs., 1 fig., 1 tab.