Accessible Requires Authentication Published by De Gruyter June 26, 2015

Analysis of safety parameters for the MINERVE reactor

Analyse von Sicherheitsparametern für den MINERVE-Reaktor
A. E. Ateya, E. H. Amin, M. E. Nagy and H. H. Abou-Gabal
From the journal Kerntechnik

Abstract

The present study aims to show the effect of different cross section libraries on MINERVE reactor safety parameters. The MCNP5 calculation model of the MINERVE reactor facility is used to determine core and safety parameters such as axial and radial fission rate distributions, control rod worth and spectral indices. Different neutron spectra were achieved by changing the experimental lattice within the MINERVE reactor. MINERVE provides a large experimental basis for the improvement of the cross section databases. The current study calculates these parameters by MCNP5 code using three different cross section libraries (the continuous energy cross sections of the ENDFB-VI, T16-2003, and ENDF/B-VII.1 libraries). Neutronic calculations were performed for R1UO2, R1MOX, R2UO2, and R2MOX core configurations, representative of a LWR loaded with UO2, mixed oxide matrix, over moderated UO2 and over moderated MOX, respectively. The study aims to determine the most suitable cross section library to be used with MCNP5 reactor calculation code for light water reactor fuel lattice. The MCNP5 results were compared with the experimental results.

Kurzfassung

Ziel dieses Beitrags ist es, den Einfluss verschiedener Wirkungsquerschnitts-Bibliotheken auf die Sicherheitsparameter des MINERVE Reaktors zu untersuchen. Das MCNP5-Rechenmodell der MINERVE-Reaktoranlage wird verwendet zur Bestimmung von Sicherheitsparametern wie z. B. axiale und radiale Spaltratenverteilung, Steuerstabgüte und spektralen Indizes. Verschiedene Neutronenspektren wurden durch Änderung des experimentellen Gitters innerhalb des MINERVE-Reaktors erzeugt. MINERVE bietet eine große experimentelle Basis für die Verbesserung von Wirkungsquerschnitts-Datenbanken. In der derzeitigen Studie werden diese Parameter mit Hilfe des MCNP5-Codes unter Verwendung von drei verschiedenen Wirkungsquerschnitts-Bibliotheken (ENDFB-VI, T16-2003 und ENDF/B-VII.1) berechnet. Neutronenphysikalische Simulationsrechnungen wurden für R1UO2, R1MOX, R2UO2, und R2MOX-Kernkonfigurationen durchgeführt. Ziel war es, die am besten geeignete Wirkungsquerschnitts-Bibliothek für die MCNP5-Berechnungen von Brennstoffgittern in Leichtwasserreaktoren zu bestimmen. Die MCNP5-Rechenergebnisse wurden mit experimentellen Ergebnissen verglichen.


* Corresponding author: E-mail:

References

1 MCNP – A General Monte Carlo N-Particle Transport Code, Version 5, April 24, 2003, Vol. I and II (Revised 10/3/05, 2/1/2008), MCNP5/MCNPX, RSICC Package CCC-740 Search in Google Scholar

2 Nuclear Engineering, Argonne National Laboratory: Modeling Report of the CEA Cadarache MINERVE Reactor for the OSMOSE Project, ANL-04/18 Search in Google Scholar

3 Mladin, M. and Mladin, D.: MCNP5 Calculations Compared to Experimental Measurements in CEA-MINERVE Reactor. U.P.B. Sci. Bull., Series D, 74 (2012) 171178 Search in Google Scholar

4 Hudelot, J. P. et. al.: MINERVE Reactor Characterization in Support of the OSMOSE Program: Safety parameters. PHYSOR 2004 – The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25–29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL Search in Google Scholar

5 Klann, R. et al.: MINERVE Reactor Characterization in Support of the OSMOSE Program: Spectral Indices. PHYSOR 2004 – The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25–29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL Search in Google Scholar

6 Nuclear Engineering, Argonne National Laboratory: Final Report of the International Nuclear Energy Research Intiative OSMOSE Project. (FY01-FY04)- ANL-04/25, December 17, 2004 Search in Google Scholar

7 Little, R. C.: MCNP Neutron Library T16-2003. LA-UR-04-4520, June 28, 2004 Search in Google Scholar

8 http://www.nndc.bnl.gov/endf/b7.1/acefiles.html Search in Google Scholar

Received: 2014-12-19
Published Online: 2015-06-26
Published in Print: 2015-07-25

© 2015, Carl Hanser Verlag, München