Validation of Minor Actinides Fission Neutron Cross-Sections
2015
Autori
Pešić, Milan P.Titarenko, Yury E.
Batyaev, Viacheslav F.
Pavlov, Kirill V.
Tffarenko, Alexey Yu.
Zhivun, Valeriy M.
Igumnov, Mikhail M.
Konev, Viacheslav N.
Legostaev, Vladimir O.
Članak u časopisu (Objavljena verzija)
Metapodaci
Prikaz svih podataka o dokumentuApstrakt
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 U-235, Np-237, (238,239,240,241)pu, (242)mAin, Cm-243, (245)cm, and Cm-247, deposited on metal support and foils of U-235 (pseudo-alloy Al-27 + U-235), U-238, In-nat, Zn-64, Al-27, and multi-component sample alloy Al-27 + (55)mn Cu-nat + Lu-nat Au-197, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF(4), 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 su...pposed 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.
Ključne reči:
nuclear data library / accelerator driven system / fast reactor actinide / reaction rate / MAKET / MCNP6.1Izvor:
Nuclear technology and radiation protection, 2015, 30, 1, 1-10Finansiranje / projekti:
- National Research Center Kurchatov Institute, Moscow
DOI: 10.2298/NTRP1501001P
ISSN: 1451-3994
WoS: 000354230200001
Scopus: 2-s2.0-84929231057
Kolekcije
Institucija/grupa
VinčaTY - JOUR AU - Pešić, Milan P. AU - Titarenko, Yury E. AU - Batyaev, Viacheslav F. AU - Pavlov, Kirill V. AU - Tffarenko, Alexey Yu. AU - Zhivun, Valeriy M. AU - Igumnov, Mikhail M. AU - Konev, Viacheslav N. AU - Legostaev, Vladimir O. PY - 2015 UR - https://vinar.vin.bg.ac.rs/handle/123456789/529 AB - 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 U-235, Np-237, (238,239,240,241)pu, (242)mAin, Cm-243, (245)cm, and Cm-247, deposited on metal support and foils of U-235 (pseudo-alloy Al-27 + U-235), U-238, In-nat, Zn-64, Al-27, and multi-component sample alloy Al-27 + (55)mn Cu-nat + Lu-nat Au-197, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF(4), 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. T2 - Nuclear technology and radiation protection T1 - Validation of Minor Actinides Fission Neutron Cross-Sections VL - 30 IS - 1 SP - 1 EP - 10 DO - 10.2298/NTRP1501001P ER -
@article{ author = "Pešić, Milan P. and Titarenko, Yury E. and Batyaev, Viacheslav F. and Pavlov, Kirill V. and Tffarenko, Alexey Yu. and Zhivun, Valeriy M. and Igumnov, Mikhail M. and Konev, Viacheslav N. and Legostaev, Vladimir O.", year = "2015", 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 U-235, Np-237, (238,239,240,241)pu, (242)mAin, Cm-243, (245)cm, and Cm-247, deposited on metal support and foils of U-235 (pseudo-alloy Al-27 + U-235), U-238, In-nat, Zn-64, Al-27, and multi-component sample alloy Al-27 + (55)mn Cu-nat + Lu-nat Au-197, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF(4), 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.", journal = "Nuclear technology and radiation protection", title = "Validation of Minor Actinides Fission Neutron Cross-Sections", volume = "30", number = "1", pages = "1-10", doi = "10.2298/NTRP1501001P" }
Pešić, M. P., Titarenko, Y. E., Batyaev, V. F., Pavlov, K. V., Tffarenko, A. Yu., Zhivun, V. M., Igumnov, M. M., Konev, V. N.,& Legostaev, V. O.. (2015). Validation of Minor Actinides Fission Neutron Cross-Sections. in Nuclear technology and radiation protection, 30(1), 1-10. https://doi.org/10.2298/NTRP1501001P
Pešić MP, Titarenko YE, Batyaev VF, Pavlov KV, Tffarenko AY, Zhivun VM, Igumnov MM, Konev VN, Legostaev VO. Validation of Minor Actinides Fission Neutron Cross-Sections. in Nuclear technology and radiation protection. 2015;30(1):1-10. doi:10.2298/NTRP1501001P .
Pešić, Milan P., Titarenko, Yury E., Batyaev, Viacheslav F., Pavlov, Kirill V., Tffarenko, Alexey Yu., Zhivun, Valeriy M., Igumnov, Mikhail M., Konev, Viacheslav N., Legostaev, Vladimir O., "Validation of Minor Actinides Fission Neutron Cross-Sections" in Nuclear technology and radiation protection, 30, no. 1 (2015):1-10, https://doi.org/10.2298/NTRP1501001P . .