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      Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method Translated title: Neutronische Leistungsberechnungen mit alternativen Fluiden in einem hybriden Reaktor unter Einsatz der Monte-Carlo-Methode

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      1
      Kerntechnik
      Carl Hanser Verlag

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          Abstract

          In this study, salt-heavy metal mixtures consisting of 93–85% Li 20Sn 80 + 5% SFG-PuO 2 and 2–10% UO 2, 93–85% Li 20Sn 80 + 5% SFG-PuO 2 and 2–10% NpO 2, and 93–85% Li 20Sn 80 + 5% SFG-PuO 2 and 2–10% UCO were used as fluids. The fluids were used in the liquid first wall, blanket, and shield zones of a fusion–fission hybrid reactor system. A beryllium (Be) zone with a width of 3 cm was used for neutron multiplicity between the liquid first wall and the blanket. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. The contributions of each isotope in the fluids to the nuclear parameters, such as tritium breeding ratio ( TBR), energy multiplication factor ( M), and heat deposition rate, of the fusion–fission hybrid reactor were calculated in the liquid first wall, blanket, and shield zones. Three-dimensional analyses were performed using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

          Kurzfassung

          In dieser Studie wurden als Liquide Salz-Schwermetallhaltige Lösungen mit 93–85% Li 20Sn 80 + 5% SFG-PuO 2 und 2–10% UO 2, 93–85% Li 20Sn 80 + 5% SFG-PuO 2 und 2–10% NpO 2, und 93–85% Li 20Sn 80 + 5% SFG-PuO 2 und 2–10% UCO verwendet. Die Liquiden wurden an der ersten Flüssigwand, am Blanket- und Shield-Bereich des hybriden Reaktorsystems eingesetzt. Für die Neutronenanreicherung wurde zwischen der ersten Flüssigwand und dem Blanket ein drei Zentimeter dicker Beryllium-Bereich (Be) angebracht. Als Baumaterial wurde vier Zentimeter dicker 9Cr2WVTa ferritischer Stahl verwendet. In dieser Studie wurde der Einfluss eines jeden Isotops auf nukleare Parameter wie dem Tritium-Erzeugungssatz (TBR) an der ersten Flüssigwand, am Blanket- und Shield-Bereich des Fusion-Fision-Hybridreaktors, dem Energie-Vervielfältigungsfaktor (M) und dem Anteil der gespeicherten Wärme berechnet.

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          Most cited references27

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          ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

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            On the exploration of innovative concepts for fusion chamber technology

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              Liquid first walls for magnetic fusion energy configurations

              R.W. Moir (1997)
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                Author and article information

                Journal
                kt
                Kerntechnik
                Carl Hanser Verlag
                0932-3902
                2195-8580
                17 March 2015
                : 80
                : 1
                : 45-52
                Affiliations
                1 İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey. E-mail: mehtap.gunay@ 123456inonu.edu.tr
                Article
                KT110479
                10.3139/124.110479
                32a74af3-a056-40bf-a279-b6d539c74f95
                © 2015, Carl Hanser Verlag, München
                History
                : 20 November 2014
                Page count
                References: 32, Pages: 8
                Categories
                Technical Contributions/Fachbeiträge

                Materials technology,Materials for energy,Nuclear physics
                Materials technology, Materials for energy, Nuclear physics

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