Abstract
In this study, the effect of (n,γ) reactions in spent fuel-grade (SFG)-PuO2, UO2, NpO2 and UCO contents was investigated in a designed hybrid reactor system. In this system, the molten salt-heavy metal mixtures 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 and 2 – 10 % UO2, 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 and 2 – 10 % NpO2, 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 and 2 – 10 % UCO were used as fluids. Beryllium (Be) is used as neutron multiplier by (n,2n) reactions. Thence, a Be zone with a width of 3 cm was used in order to contribute on fissile fuel breeding between the liquid first wall and blanket. (n,γ) reactions were calculated in the liquid first wall, blanket and shield zones, which SFG-PuO2, UO2, NpO2 and UCO contents. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code and nuclear data library ENDF/B-VII.0.
Kurzfassung
In dieser Studie wurden in einem konzipierten Reaktorsystem (n,γ) Reaktionen bei Spent-Fuel-grade Komponenten (SFG)-PuO2, UO2, NpO2 und UCO untersucht. In diesem System wurden als Fluide gelöste Salz-Schwermetal-Mischungen aus 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 und 2 – 10 % UO2, 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 und 2 – 10 % NpO2, 93 – 85 % Li20Sn80 + 5 % SFG-PuO2 und 2 – 10 % UCO verwendet. Beryllium wird über die (n, 2n) Reaktion als Neutronenmultiplikator verwendet. Deshalb wurde zwischen der ersten Flüssigwand und dem Blankett ein 3 cm dicker Be-Bereich eingesetzt, um so die Herstellung von spaltbarem Brennstoff zu fördern. Die (n,γ) Reaktion wurde an der aus SFG-PuO2, UO2, NpO2 und UCO, bestehenden ersten Flüssigwand, am Blankett- und am Shield-Bereich berechnet. Als Baumaterial wurde ein vier Zentimeter dicker ferritischer Stahl – 9Cr2WVTa – verwendet. Dreidimensionale nukleonische Berechnungen wurden mit Hilfe der neuesten Version des Monte Carlo Codes MCNPX-2.7.0 und unter Verwendung der nuklearen Datenbibliothek ENDF/B-VII.0 durchgeführt.
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