The effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport code

Günay, Mehtap; Şarer, Başar; Kasap, Hızır

doi:10.1016/j.anucene.2013.07.038

Cited by 8 publications

(2 citation statements)

References 18 publications

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“…Thus, the high energy fusion neutrons convert fertile materials to fissile fuel, fission neutrons, and produce energy. The hybrid reactor produces 30 times more nuclear fuel per nuclear energy quantity than fast reactors [1][2][3][4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Three-dimensional Monte Carlo calculation of some nuclear parameters

Günay

Şeker

2017

EPJ Web Conf.

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Abstract. In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li 20 Sn 80 + 1-5% RG-Pu, 99-95% Li 20 Sn 80 + 1-5% RG-PuF 4 , and 99-95% Li 20 Sn 80 + 1-5% RG-PuO 2 , as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Threedimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

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Section: Introductionmentioning

confidence: 99%

Three-dimensional Monte Carlo calculation of some nuclear parameters

Günay

Şeker

2017

EPJ Web Conf.

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“…Hybrid reactor has an enormous potential to provide a clean, cheap and unlimited energy source. Important advantage of hybrid reactor system is that it has a subcritical reactor system in which reactor can operate securely [1][2][3][4][5][6].…”

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confidence: 99%

Contributions of each isotope in structural material on radiation damage in a hybrid reactor

Günay

2016

EPJ Web Conf.

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In this study, the fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. In this study, salt-heavy metal mixtures consisting of 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UO 2 , 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% NpO 2 , and 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO 2 , UO 2 , NpO 2 and UCO contents was investigated in the structural material of a designed fusion-fission hybrid reactor system. In the designed hybrid reactor system were investigated the effect on the radiation damage of the selected fluid according to each isotopes of structural material in the structural material 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.

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Flexibly-Bounded Rationality in Interstate Conflict

Marwala

2014

Artificial Intelligence Techniques for Rational Decision Making

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The effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport code

Cited by 8 publications

References 18 publications

Three-dimensional Monte Carlo calculation of some nuclear parameters

Three-dimensional Monte Carlo calculation of some nuclear parameters

Contributions of each isotope in structural material on radiation damage in a hybrid reactor

Flexibly-Bounded Rationality in Interstate Conflict

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