Research on experimental reactors, such as HTR-10, provide useful data about potentialities of very high temperature gas-cooled reactors (VHTR). The latter is today rated as one of the six nuclear reactor types involved in the Generation-IV International Forum (GIF) Initiative. In this study, the MCNP5 code has been employed to evaluate the neutron radiation trend vs. the biological shield's thickness and to calculate the neutron effective dose rate at the outer surface. The reactor's geometry has been completely modeled by means of lattices and universes provided by MCNP, even though some approximations were required. Monte Carlo calculations have been performed by means of a simple PC and, as a consequence, in order to obtain acceptable run times, it was made an extensive recourse to variance reduction methods. (C) 2011 Elsevier BM. All rights reserved.

Monte carlo calculation of the neutron effective dose rate at the outer surface of the biological shield of HTR-10 reactor / Remetti, Romolo; Giulio, Andreoli; Silvina, Keshishian. - In: NUCLEAR ENGINEERING AND DESIGN. - ISSN 0029-5493. - STAMPA. - 243:(2012), pp. 148-152. [10.1016/j.nucengdes.2011.12.003]

Monte carlo calculation of the neutron effective dose rate at the outer surface of the biological shield of HTR-10 reactor

REMETTI, Romolo;
2012

Abstract

Research on experimental reactors, such as HTR-10, provide useful data about potentialities of very high temperature gas-cooled reactors (VHTR). The latter is today rated as one of the six nuclear reactor types involved in the Generation-IV International Forum (GIF) Initiative. In this study, the MCNP5 code has been employed to evaluate the neutron radiation trend vs. the biological shield's thickness and to calculate the neutron effective dose rate at the outer surface. The reactor's geometry has been completely modeled by means of lattices and universes provided by MCNP, even though some approximations were required. Monte Carlo calculations have been performed by means of a simple PC and, as a consequence, in order to obtain acceptable run times, it was made an extensive recourse to variance reduction methods. (C) 2011 Elsevier BM. All rights reserved.
2012
4th generation; htr-10; monte carlo; nuclear reactors; radioprotection
01 Pubblicazione su rivista::01a Articolo in rivista
Monte carlo calculation of the neutron effective dose rate at the outer surface of the biological shield of HTR-10 reactor / Remetti, Romolo; Giulio, Andreoli; Silvina, Keshishian. - In: NUCLEAR ENGINEERING AND DESIGN. - ISSN 0029-5493. - STAMPA. - 243:(2012), pp. 148-152. [10.1016/j.nucengdes.2011.12.003]
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/433160
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