Nuclear Technology & Radiation Protection Journal


NT & RP Journal	VALIDATION OF MINOR ACTINIDES FISSION NEUTRON CROSS-SECTIONS
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Vol. XXX, No. 1, Pp. 237-340 March 2015 UDC 621.039+614.876:504.06 ISSN 1451-3994 Back to Contents	Pages: 01-10 Authors: Milan P. Pešić, Yury E. Titarenko, Viacheslav F. Batyaev, Kirill V. Pavlov, Alexey Yu. Titarenko, Valeriy M. Zhivun, Mikhail M. Igumnov, Viacheslav N. Konev, and Vladimir O. Legostaev Abstract Verification of neutron fission cross-sections of minor actinides from some recently available evaluated nuclear data libraries was carried out by comparison of the reaction rates calculated by the MCNP6.1 computer code to the experimental values. The experimental samples, containing thin layers of ²³⁵U,²³⁷Np, ²³⁸^,²³⁹^,240,241Pu, ^242mAm, ²⁴³Cm, ²⁴⁵Cm, and ²⁴⁷Cm, deposited on metal support and foils of ²³⁵U (pseudo-alloy ²⁷Al + ²³⁵U), ²³⁸U, natIn, ⁶⁴Zn, ²⁷Al, and multi-component sample alloy ²⁷Al + ⁵⁵Mn + ^natCu + ^natLu + ¹⁹⁷Au, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF₄, labelled as the Micromodel Salt Blanket, inserted in the lattice centre of the MAKET heavy water critical assembly at the Institute for Theoretical and Experimental Physics, Moscow. This paper is a continuation of earlier initiated scientific-research activities carried out for validation of the evaluated fission cross-sections of actinides that were supposed to be used for the quality examination of the fuel design of the accelerator driven systems or fast reactors, and consequently, determination of transmutation rates of actinides, and therefore, determination of operation parameters of these reactor facilities. These scientific-research activities were carried out within a frame of scientific projects supported by the International Science and Technology Center and the International Atomic Energy Agency co-ordinated research activities, from 1999 to 2010. Obtained results confirm that further research is needed in evaluations in order to establish better neutron cross-section data for the minor actinides and selected nuclides which could be used in the accelerator driven systems or fast reactors. Key words: nuclear data library, accelerator driven system, fast reactor, actinide, reaction rate, MAKET, MCNP6.1 FULL PAPER IN PDF FORMAT (4.16 MB)
Vinča Institute of Nuclear Sciences :: Designed by milas :: July 2007 Operated by acapanic :: Last updated on May, 2015

Pages: 01-10

Authors: Milan P. Pešić, Yury E. Titarenko, Viacheslav F. Batyaev, Kirill V. Pavlov, Alexey Yu. Titarenko, Valeriy M. Zhivun, Mikhail M. Igumnov, Viacheslav N. Konev, and Vladimir O. Legostaev

Abstract

Verification of neutron fission cross-sections of minor actinides from some recently available evaluated nuclear data libraries was carried out by comparison of the reaction rates calculated by the MCNP6.1 computer code to the experimental values. The experimental samples, containing thin layers of ²³⁵U,²³⁷Np, ²³⁸^,²³⁹^,240,241Pu, ^242mAm, ²⁴³Cm, ²⁴⁵Cm, and ²⁴⁷Cm, deposited on metal support and foils of ²³⁵U (pseudo-alloy ²⁷Al + ²³⁵U), ²³⁸U, natIn, ⁶⁴Zn, ²⁷Al, and multi-component sample alloy ²⁷Al + ⁵⁵Mn + ^natCu + ^natLu + ¹⁹⁷Au, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF₄, labelled as the Micromodel Salt Blanket, inserted in the lattice centre of the MAKET heavy water critical assembly at the Institute for Theoretical and Experimental Physics, Moscow. This paper is a continuation of earlier initiated scientific-research activities carried out for validation of the evaluated fission cross-sections of actinides that were supposed to be used for the quality examination of the fuel design of the accelerator driven systems or fast reactors, and consequently, determination of transmutation rates of actinides, and therefore, determination of operation parameters of these reactor facilities. These scientific-research activities were carried out within a frame of scientific projects supported by the International Science and Technology Center and the International Atomic Energy Agency co-ordinated research activities, from 1999 to 2010. Obtained results confirm that further research is needed in evaluations in order to establish better neutron cross-section data for the minor actinides and selected nuclides which could be used in the accelerator driven systems or fast reactors.

Key words: nuclear data library, accelerator driven system, fast reactor, actinide, reaction rate, MAKET, MCNP6.1

FULL PAPER IN PDF FORMAT (4.16 MB)