- Tytuł:
- Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code
- Autorzy:
- Günay, M.
- Powiązania:
- https://bibliotekanauki.pl/articles/1401933.pdf
- Data publikacji:
- 2015-08
- Wydawca:
- Polska Akademia Nauk. Instytut Fizyki PAN
- Tematy:
-
28.52.-s
28.52.Av - Opis:
- In this study, the effect of the radiation damage of spent fuel-grade plutonium content was investigated in the structural material of a designed fusion-fission hybrid reactor system. In this study, the molten salt-heavy metal mixtures 99-95% $Li_{20}Sn_{80}-1-5%$ SFG-Pu, 99-95% $Li_{20}Sn_{80}-1-5%$ $SFG-PuF_{4}$, and 99-95% $Li_{20}Sn_{80}-1-5%$ $SFG-PuO_{2}$ were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In this study, damage to the total structural material and each 1.0 cm thickness thereof was measured as a function of radiation energy, using the selected fluid rates, for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.
- Źródło:
-
Acta Physica Polonica A; 2015, 128, 2B; B-113-B-117
0587-4246
1898-794X - Pojawia się w:
- Acta Physica Polonica A
- Dostawca treści:
- Biblioteka Nauki
Artykuł