Published August 1990 | Version v1
Journal article

The use of statistical methods for assessing correction factors for assembly outlet coolant temperatures in the reactor core

Creators

  • 1. Vyskumny Ustav Jadrovych Elektrarni, Trnava (Czechoslovakia)

Description

An algorithm was set up for calculations of the so-called coolant temperature correction coefficients at the outlets from fuel assemblies; it is based on the regression method with regression curve order estimation. The algorithm has been tested in the Bohunice V-1 nuclear power plant. It can be implemented on minicomputers or microcomputers. Its drawbacks include high requirements put on the intermediate results buffer capacity and high costs required for testing the likelihood of the input data in the calculation part of the algorithm. (Z.M.). 2 figs., 1 tab., 7 refs

Additional details

Additional titles

Original title (Slovak)
Pouzitie statistickych metod pri urcovani hodnot opravnych koeficientov teplot chladiva na vystupe z kaziet v aktivnej zone jadroveho reaktora

Publishing Information

Journal Title
Jaderna Energie
Journal Volume
36
Journal Issue
8
Series
Jad. Energ.
Journal Page Range
309-313
ISSN
0448-116X
CODEN
JADEA

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Serbia and Montenegro
INIS RN
22023185
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ALGORITHMS; COMPUTER CALCULATIONS; CORRECTIONS; FUEL ASSEMBLIES; REACTOR CORES; REGRESSION ANALYSIS; TEMPERATURE COEFFICIENT; WATER
Descriptors DEC
HYDROGEN COMPOUNDS; MATHEMATICS; OXYGEN COMPOUNDS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; STATISTICS

Optional Information

Notes
English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia, at US$ 10 per typewritten page.