Abstract
In this paper, the effects of using FLiBe and FLiNaBe Molten Salts Bearing Plutonium Fluorides on the neutronic performance of the PACER are investigated. The optimum radial thickness for tritium self-sufficiency of the blankets addition of plutonium fluorides to FLiNaBe (LiF-/NaF BeF2) and FLiBe (LiF-/BeF2) of a dual purpose modified PACER concept are determined. The calculations are carried out with the one dimensional transport code XSDRNPM/SCALE5. The tritium breeding capacities of FLiNaBe and FLiBe with addition of plutonium fluorides in molten salt zone are investigated and compared. The optimum molten salt zone thickness is computed as 155 cm for tritium self-sufficiency of the blankets using FLiBe +1% PuF4 whereas, the optimum thickness with FLiNaBe +1% PuF4 is calculated as 170 cm. In addition, neutron transport calculations have been performed to evaluate the energy multiplication factor, total fission rate, displacement per atom and helium gas generation for optimal radial thickness in the blanket. Also, the tritium production and the radiation damage limits should be evaluated together in a fusion blanket for determining the optimum thickness of molten salt layer.
Kurzfassung
In sog. PACER-Reaktorkonzept wird durch (unterirdisch stattfindende) Explosionen Energie in Flüssigsalzen freigesetzt. Die Flüssigsalze geben diese Energie über einen Wärmetauscher an Wasser ab. Der so gewonnene Wasserdampf treibt die mit dem Generator verbundene Turbine an. Dabei fungieren die Flüssigsalze gleichzeitig als Kühlmittel und als Tritiumbrutzone. In diesem Beitrag wird der Einfluss des Zusatzes von Plutoniumfluoriden zu den Flüssigsalzen u.a. auf die selbsterhaltende Tritiumbrutkapazität untersucht. Die Berechnungen mit dem 1D-Programm XSDRNPM/SCALE5 bestimmen eine für eine selbsterhaltende Tritium-brutreaktion optimale Dicke der Flüssigsalzzone von 155 cm für die Mischung aus FLiBe +1% PuF4 und eine optimal Dicke von 170 cm für die Mischung von FLiNaBe +1% PuF4.
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