Published 1975 | Version v1
Miscellaneous Open

Study of the influence of slab perturbation in the cell on the fuel local burnup

Creators

  • 1. Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

Description

The influence of construction material or voids in the fuel element on the fuel burnup was the objective of this study. Experiments were done by cell perturbation method. Theoretical method was developed for calculating the effect of reactor cell perturbation. Obtained results both experimental and theoretical clearly indicate that the minimum quantity of construction material or void cause local increase of neutron flux in the mentioned regions. This increase of flux which amounts to nearly ten percent, and can reach the value of a few tens percent leads to the local increase of fuel burnup

Availability note (English)

Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca

Abstract (Serbian)

U radu je izucavan uticaj konstrukcionog materijala ili supljina u sklopu gorivnog elementa na lokalno izgaranje nuklearnog goriva. Eksperimenti su radjeni metodom perturbacije celije. Razvijena je teorijska metoda za proracun ovog efekta perturbacije celije. Dobijeni rezultati, kako eksperimentalni tako i teorijski jasno ukazuju da i najmanja kolicina konstrukcionog materijala ili pak supljina dovodi do lokalnog porasta fluksa neutrona u pomenutim oblastima. Ovo povecanje fluksa koje u najpovoljnijem slucaju iznosi blizu desetak procenata, a moze biti i reda nekoliko desetina procenata, dovodi do lokalnog porasta izgaranja goriva (author)

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Additional details

Additional titles

Original title (Serbian)
Izucavanje uticaja plocaste perturbacije celije na lokalno izgaranje goriva

Publishing Information

Imprint Pagination
16 p.
Report number
INIS-RS--0049

INIS

Country of Publication
Serbia
Country of Input or Organization
Serbia
INIS RN
38013774
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BURNUP; CALCULATION METHODS; CLADDING; DISTURBANCES; EXPERIMENTAL DATA; FUEL ELEMENTS; NEUTRON FLUX; REACTOR CELLS; VOIDS
Descriptors DEC
DATA; DEPOSITION; INFORMATION; NUMERICAL DATA; RADIATION FLUX; REACTOR COMPONENTS; SURFACE COATING

Optional Information

Notes
5 refs, 2 tabs, 3 figs
Secondary number(s)
IBK--1372