The production of 238–242Pu(n,γ)239–243Pu fissionable fluids in a fusion-fission hybrid reactor

M. Günay

doi:10.3139/124.110364

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The production of ^238–242Pu(n,γ)^239–243Pu fissionable fluids in a fusion-fission hybrid reactor

M. Günay

Published/Copyright: March 12, 2014

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From the journal Kerntechnik Volume 79 Issue 1

Abstract

In this study, the effect of spent fuel grade plutonium content on ^239–243Pu was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-Pu, 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-PuF₄, 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-PuO₂. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of ^238–242Pu(n,γ)^239–243Pu was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0.

Kurzfassung

In diesem Beitrag wurde der Effekt des Plutoniumgehaltes von abgebranntem Kernbrennstoff auf ^239–243Pu in einem neu konzipierten Hybridreaktor untersucht. In diesem System waren die Flüssigkeiten zusammengesetzt aus geschmolzenem Salz und einem Schwermetallgemisch mit steigenden Molfraktionen 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-Pu, 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-PuF₄, 99 – 95 % Li₂₀Sn₈₀-1 – 5 % SFG-PuO₂. Beryllium ist ein Neutronenmultiplikator mittels (n,2n) Kernreaktionen. Deshjalb wird eine Be-Zone von 3 cm Dicke verwendet, um so zur Erzeugung spaltbaren Materials zwischen der flüssigen ersten Wand und einer Brutzone aus 9Cr2WVTa ferritischem Stahl beizutragen. Die Erzeugung von ^238–242Pu(n,γ)^239–243Pu wurde in der flüssigen ersten Wand, sowie in den Brut- und Abschirmzonen berechnet. Für die dreidimensionalen Berechnungen wurde die aktuelle Version des Monte Carlo Codes MCNPX-2.7.0 und die Kerndatenbibliothek ENDF/B-VII.0 verwendet.

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Received: 2013-06-04

Published Online: 2014-03-12

Published in Print: 2014-03-17

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https://doi.org/10.3139/124.110364