Published 2005 | Version v1
Journal article Metadata-only

Computational management of the BN-600 reactor operation

Creators

  • 1. Beloyarskaya AEhS, Zarechnyj (Russian Federation)

Description

Major design features of the core in the period of the BN-600 reactor operation are provided. Analysis of neutronic calculations of the BN-600 reactor using the URAN and GEFEST software complexes was made. Influence of the method of the BN-600 reactor calculations using the GEFEST software complex on the results of fuel assembly design characteristics is estimated

Abstract (Russian)

Приведены основные отличительные характристики активных зон за время эксплуатации реактора БН-600. Проведен анализ нейтронно-физических расчетов реактора БН-600 комплексом программ URAN и комплексом программ ГЕФЕСТ. Приведена оценка влияния методики расчетов реактора БН-600 комплексом программ ГЕФЕСТ на результаты расчетных характеристик

Additional details

Additional titles

Original title (Russian)
Расчетное сопровождение эксплуатации реактора BN-600

Publishing Information

Journal Title
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Journal Issue
no.1
Journal Page Range
p. 60-65
ISSN
0204-3327

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
37094565
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BELOYARSK-3 REACTOR; FUEL ASSEMBLIES; G CODES; ISOTOPE RATIO; MULTIPLICATION FACTORS; PARAMETRIC ANALYSIS; PERFORMANCE; REACTIVITY COEFFICIENTS; REACTOR CORES; REACTOR OPERATION; SPATIAL DISTRIBUTION; U CODES
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; DIMENSIONLESS NUMBERS; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Notes
4 refs., 2 tabs.