CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations-Reference-Cited by-同舟云学术

CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations

Published:2011-08 Issue:8 Volume:241 Page:2927-2932
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Boulaich Y.,El Bardouni T.,Erradi L.,Chakir E.,Boukhal H.,Nacir B.,El Younoussi C.,El Bakkari B.,Merroun O.,Zoubair M.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference21 articles.

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3. Erradi, L., 1982. Etude des effets de températures dans les réseaux caractéristiques des réacteurs nucléaires de la filière à eau ordinaire. PhD Thesis, Université de Paris Sud Orsay.

4. Erradi, L., 2007. Creole PWR reactivity temperature coefficient experiment. Cea Report, CEA/Cadarche/DER/SPRC.

5. Erradi, L., Santamarina, A., 2008. Interprétation de l’expérience CREOLE sur le coefficient de température des REP UOX et MOX par les codes APOLLO2.8 et TRIPOLI4.5 avec la bibliothèque JEFF3.1.1. Note technique de cea, Novembre.

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1. Study on criticality and reactivity coefficients of VVER-1200 reactor;Progress in Nuclear Energy;2021-01

2. 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;Nuclear Engineering and Technology;2020-06

3. Study of minor actinides effect on kinetic parameters and reactivity coefficients in an accelerator driven system;Progress in Nuclear Energy;2015-08

4. Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel;Annals of Nuclear Energy;2014-09