This work was carried out in the framework of the EU FP7 project MAXSIMA “Methodology, Analysis and eXperiments for the "Safety In MYRRHA Assessment”. The MAXSIMA WP2 deals with the safety analyses to support the licensing of MYRRHA (planned to be built by 2023 at the SCK-CEN research center in Mol, Belgium) and Task 2.1 is devoted to the neutronic and shielding analyses in support of safety studies. The neutronic parameters (for TH safety studies) have to be evaluated through the analysis of envelope cases - minimum and maximum cores in both critical and sub-critical operational modes - yielding the possible working range of the MYRRHA core. The report summarizes the presentation done by the author in the SEARCH-MAXSIMA meeting on November 28-29th, 2013, at the Von Karman Institute in Rhode-Saint-Genèse (B). He showed the neutronic model of the MYRRHA-MAXSIMA core, together with the thermo-physical properties of materials assumed for the analysis. Based on the minimum critical and sub-critical core layouts with fresh fuel and no In-Pile Sections for samples irradiation (defined in the previous meeting in May 2013; UTFISSM-P9B2-001), he reported their complete neutronic analysis at 20 °C, 200 °C and in nominal conditions with the ERANOS 2.2 deterministic code. The analysis includes the reactivity feedbacks / coefficients due to temperature effects, as well as the impact on core reactivity of all possible accident situations in both operational modes. Furthermore, he shown a first investigation on maximum cores, having equilibrium fuel compositions and some In-Pile Sections inserted in the core layout.

Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code

Sarotto, Massimo
2013

Abstract

This work was carried out in the framework of the EU FP7 project MAXSIMA “Methodology, Analysis and eXperiments for the "Safety In MYRRHA Assessment”. The MAXSIMA WP2 deals with the safety analyses to support the licensing of MYRRHA (planned to be built by 2023 at the SCK-CEN research center in Mol, Belgium) and Task 2.1 is devoted to the neutronic and shielding analyses in support of safety studies. The neutronic parameters (for TH safety studies) have to be evaluated through the analysis of envelope cases - minimum and maximum cores in both critical and sub-critical operational modes - yielding the possible working range of the MYRRHA core. The report summarizes the presentation done by the author in the SEARCH-MAXSIMA meeting on November 28-29th, 2013, at the Von Karman Institute in Rhode-Saint-Genèse (B). He showed the neutronic model of the MYRRHA-MAXSIMA core, together with the thermo-physical properties of materials assumed for the analysis. Based on the minimum critical and sub-critical core layouts with fresh fuel and no In-Pile Sections for samples irradiation (defined in the previous meeting in May 2013; UTFISSM-P9B2-001), he reported their complete neutronic analysis at 20 °C, 200 °C and in nominal conditions with the ERANOS 2.2 deterministic code. The analysis includes the reactivity feedbacks / coefficients due to temperature effects, as well as the impact on core reactivity of all possible accident situations in both operational modes. Furthermore, he shown a first investigation on maximum cores, having equilibrium fuel compositions and some In-Pile Sections inserted in the core layout.
Rapporto Tecnico, MAXSIMA WP2, Task 2.1;Fisica del reattore;Neutronica;T/H
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/7610
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