Published 1971 | Version v1
Miscellaneous Open

Nondestructive analysis of RA reactor fuel burnup, Program for burnup calculation base on relative yield of 106Ru, 134Cs and 137Cs in the irradiated fuel

Creators

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

Description

Burnup of low enriched metal uranium fuel of the RA reactor is described by two chain reactions. Energy balance and material changes in the fuel are described by systems of differential equations. Numerical integration of these equations is base on the the reactor operation data. Neutron flux and percent of Uranium-235 or more frequently yield of epithermal neutrons in the neutron flux, is determined by iteration from the measured contents of 106Ru, 134Cs and 137Cs in the irradiated fuel. The computer program was written in FORTRAN-IV. Burnup is calculated by using the measured activities of fission products. Burnup results are absolute values

Availability note (English)

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

Abstract (Serbian)

Sagorevanje maloobogacenog uranskog metalnog goriva reaktora RA je opisano dvema lancanim reakcijama. Energetski bilans i materijalne promene u gorivu su opisane sistemima diferencijalnih jednacina. Numericka integracija jednacina se vrsi na osnovu podataka u dinamici rada reaktora. Fluks reaktorskih neutrona i procenat urana-235 ili ucesce epitermalnih neutrona u fluksu, odredjuje se iterativno na osnovu izmerenog sadrzaja 106Ru, 134Cs i 137Cs u ozracenom gorivu. Program je napisan u FORTRAN-u IV u jednom bloku, bez podprograma. Izracunavanje izgaranja je zasnovano na izmerenim kolicnicima aktivnosti fisionih produkata. Rezultati izgaranja imaju apsolutni karakter (author)

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Additional details

Additional titles

Original title (Serbian)
Nedestruktivno odredjivanje izgaranja goriva reaktora RA, Program za izracunavanje izgaranja na osnovu relativne zastupljenosti

Publishing Information

Imprint Pagination
34 p.
Report number
INIS-RS--0037

INIS

Country of Publication
Serbia
Country of Input or Organization
Serbia
INIS RN
38013762
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; CESIUM 134; CESIUM 137; COMPUTER CALCULATIONS; EPITHERMAL NEUTRONS; FISSION PRODUCTS; ITERATIVE METHODS; NEUTRON FLUX; R-A REACTOR; RUTHENIUM 106; SLIGHTLY ENRICHED URANIUM
Descriptors DEC
ACTINIDES; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CESIUM ISOTOPES; ELECTRON CAPTURE RADIOISOTOPES; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; FERMIONS; HADRONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MATERIALS; METALS; NEUTRONS; NUCLEI; NUCLEONS; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIATION FLUX; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; RUTHENIUM ISOTOPES; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
24 refs, 1 tab, 10 figs
Secondary number(s)
IBK--1020