Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

• Authors: M. Günay
• Languages of publication: EN

Abstracts

EN

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.

Keywords

EN

28.52.-s; 28.52.Av

Discipline

• 28.52.-s: Fusion reactors(see also 52.55.-s Magnetic confinement and equilibrium, 52.57.-z Laser inertial confinement, and 52.58.-c Other confinement methods in physics of plasmas; 89.30.Jj Nuclear fusion power in energy resources)
• 28.52.Av: Theory, design, and computerized simulation

• Publisher: Institute of Physics, Polish Academy of Sciences
• Journal: Acta Physica Polonica A
• Year: 2015
• Volume: 128
• Issue: 2B
• Pages: B-113-B-117

Dates

published

2015-8

Contributors

author

M. Günay

• İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey

References

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Identifiers

DOI

10.12693/APhysPolA.128.B-113