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Radioactivity and decay heat analysis of the MNSR with HEU and LEU fuels using the GETERA code

Radioactivity and decay heat analysis of the MNSR with HEU and LEU fuels using the GETERA code
S. Dawahra; K. Khattab; G. Saba
International Journal of Nuclear Energy Science and Technology, Vol. 11, No. 1 (2017) pp. 56 - 71
The knowledge of the decay heat of nuclear fuel is necessary for performing the reactor safety analysis. In this study, analysis of the radioactivity, decay heat and the isotopic mass variation with time post the shutdown of the Miniature Neutron Source Reactor (MNSR) for the potential LEU fuels (U<SUB align="right">3Si<SUB align="right">2-Al, U<SUB align="right">3Si-Al, U<SUB align="right">9Mo-Al, 19.75% enriched and UO<SUB align="right">2, 12.6% enriched) and the existing HEU fuel (UAl<SUB align="right">4-Al, 90% enriched) have been performed using the GETERA code. The results showed that the total radioactivities were 2.13E05, 2.58E05, 2.59E05, 2.13E05 and 2.57E05 Ci, and the total decay heats were 1379.9, 1677.0, 1677.2, 1380.6 and 1672.6 W instantly after the reactor shutdown for the LEU and HEU-UAl<SUB align="right">4 cores respectively. Finally, good agreements were noticed between the analytical, ORIGEN-2 and GETERA results.

Authors:   S. Dawahra; K. Khattab; G. Saba
Journal:   International Journal of Nuclear Energy Science and Technology
Volume:   11
edition:   1
Year:   2017
Pages:   56
DOI:   10.1504/IJNEST.2017.085079
Publication date:   11-Jul-2017
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  • safety
  • radioactivity
  • neutron
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