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Bitelli, Ulysses d'Utra; Mura, Luis Felipe L.; Fanaro, Leda C.C.B., E-mail: ubitelli@ipen.br, E-mail: lflmura@ipen.br, E-mail: lcfanaro@ipen.br
Associacao Brasileira de Energia Nuclear, Rio de Janeiro, RJ (Brazil)2009
Associacao Brasileira de Energia Nuclear, Rio de Janeiro, RJ (Brazil)2009
AbstractAbstract
[en] This work presents the measures of the nuclear reaction rates along of the radial direction of the fuel pellet by irradiation and posterior gamma spectrometry of a thin slice of fuel pellet of UO2 at 4.3% enrichment. From its irradiation the rate of radioactive capture and fission are measures as a function of the radius of the pellet disk using a HPGe detector. Diverse lead collimators of changeable diameters have been used for this purpose. Simulating the fuel pellet in the pin fuel of the IPEN/MB-01 reactor, a thin disk is used, being inserted in the interior of a dismountable fuel rod. This fuel rod is then placed in the central position of the IPEN/MB-01 reactor core and irradiated during 1 hour under a neutron flux of 5.108 n/cm2s. The nuclear reaction of radioactive capture occurs in the atoms of U-238 that when absorbs a neutron transmutes into U-239 of half-life of only 23 minutes. Thus, it is opted for the detection of the Np-239, radionuclide derivative of the radioactive decay of the U-239 and that has a measurable half-life (2.335 days). In gamma spectrometry 11 collimators with different diameters have been used, consequently, the gamma spectrometry is made in function of the diameter (radius) of the irradiated UO2 fuel pellet disk, thus is possible to get the average value of the counting for each collimator in function of the specific pellet radius. These values are directly proportional to the radioactive capture nuclear reaction rates. The same way the nuclear fission rate occurs in the atoms of the U-235 that produce different fission products such as Ce-143 with a yield fission of 5.9% and applying the same procedure the fission nuclear reaction rate is obtained. This work presents some calculated values of nuclear reaction rate of radioactive capture and fission along of the radial direction of the fuel pellet obtained by Monte Carlo methodology using the MCNP-4C code. The relative values obtained are compared with experimental values and show a good agreement between experimental and calculated values. Besides nuclear reaction rates, the spectral indices28 ρ and 25δ have been obtained at each different values of the radius of the fuel pellet disk. (author)
Primary Subject
Source
2009; [11 p.]; INAC 2009: International nuclear atlantic conference. Innovations in nuclear technology for a sustainable future; Rio de Janeiro, RJ (Brazil); 27 Sep - 2 Oct 2009; 16. Brazilian national meeting on reactor physics and thermal hydraulics; Rio de Janeiro, RJ (Brazil); 27 Sep - 2 Oct 2009; 9. Brazilian national meeting on nuclear applications; Rio de Janeiro, RJ (Brazil); 27 Sep - 2 Oct 2009; 1. Meeting on Nuclear Industry; Rio de Janeiro, RJ (Brazil); 27 Sep - 2 Oct 2009; 7 refs., 12 figs., 6 tabs. Published only in CD-Rom. Code: r01634fullpaper.pdf
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHALCOGENIDES, COMPUTER CODES, DATA, DAYS LIVING RADIOISOTOPES, EVEN-ODD NUCLEI, EXPERIMENTAL REACTORS, FUEL ELEMENTS, HEAVY NUCLEI, INFORMATION, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MINUTES LIVING RADIOISOTOPES, NEPTUNIUM ISOTOPES, NUCLEI, NUMERICAL DATA, ODD-EVEN NUCLEI, OXIDES, OXYGEN COMPOUNDS, PELLETS, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SPECTROSCOPY, SPONTANEOUS FISSION RADIOISOTOPES, URANIUM COMPOUNDS, URANIUM ISOTOPES, URANIUM OXIDES, YEARS LIVING RADIOISOTOPES, ZERO POWER REACTORS
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