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

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

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자료유형: 학술저널

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

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제6호

발행연도: 2020.1

수록면: 1,120 - 1,130 (11page)

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The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO2 lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/ C. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO2 lattice configuration, we have also analyzed integral measurements in UO2 clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar

참고문헌 (13)

참고문헌 신청

CEA / 2008 / CREOLE PWR Reactivity Temperature Coefficient Experiment, Centre de Cadarache

L. ERRADI / 2003 / The reactivity temperature coefficient analysis in light water moderated UO2 and UO2-PuO2 lattices / Nucl. Sci. Eng 144:47~74

Denise B. Pelowitz / 2014 / MCNP6TM USER’S MANUAL

Y. Boulaich / 2011 / CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations / Nucl. Eng. Des 241(8):2927~2932

Forrest B. Brown / 2006 / The Makxsf Code with Doppler Broadening

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