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AbstractAbstract
[en] Possibility of determination of the neutron flux in the fuel of a heavy water reactor has been examined. In determination of the flux an iterative procedure was used to compare calculated and measured contents of several fission products. The former contents were determined by calculation of the burning process balance and the latter by non-destructive gamma-spectrometric analysis of fuel. The obtained results prove the possibility of such determination of not only the average value of the flux but also of the change of its intensity during utilization of fuel (author)
[sr]
U radu je ispitivana mogucnost odredjivanja fluksa neutrona u gorivu teskovodnog nuklearnog reaktora. Pri odredjivanju fluksa koriscen je iterativni postupak, u kome se porede izracunati i izmereni sadrzaji nekoliko gama-radioaktivnih fisionih produkata. Prvi sadrzaji su odredjivani preko proracuna bilansa procesa sagorevanja, a drugi - nedestruktivnom gama-spektrometrijskom analizom goriva. Dobijeni rezultati potvrdjuju mogucnost ovakvog odredjivanja ne samo srednje vrednosti fluksa, vec i promene njegovog intenziteta u toku koriscenja goriva (author)Primary Subject
Source
Sep 1979; 27 p; IBK--1489; Also available from the Institute of nuclear sciences Vinca; 14 refs, 3 tabs, 6 figs
Record Type
Miscellaneous
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Country of publication
CALCULATION METHODS, CHEMICAL ANALYSIS, ENRICHED URANIUM REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, ISOTOPES, MATERIALS, RADIATION FLUX, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SPECTROSCOPY, TANK TYPE REACTORS, THERMAL REACTORS
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