Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library-Reference-Cited by-同舟云学术

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Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library

Published:2020-06 Issue:6 Volume:52 Page:1120-1130
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

El Ouahdani S.,Erradi L.,Boukhal H.,Chakir E.,El Bardouni T.,Boulaich Y.,Ahmed A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

1. CREOLE PWR Reactivity Temperature Coefficient Experiment;CEA/SPRC,2008

2. The reactivity temperature coefficient analysis in light water moderated UO2 and UO2 -PuO2 lattices;ERRADI;Nucl. Sci. Eng.,2003

3. “MCNP6TM USER’S MANUAL”, Code Version 6.1.1beta, LA-CP-14-00745;Pelowitz,2014

4. CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations;Boulaich;Nucl. Eng. Des.,2011

5. “The Makxsf Code with Doppler Broadening”, LA-UR-06-7002;Brown,2006

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1. Production of high-energy neutrons by interaction of a deuteron beam with matter;Applied Radiation and Isotopes;2021-08

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