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A. Vasiliev,E. Kolbe,H. Ferroukhi,R. Pittarello 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The paper refers to an analysis of the `H.B. Robinson-2 Pressure Vessel Benchmark' with the MCNPX code. The benchmark is based on an experiment performed at an operating PWR reactor and includes measurements for both in-vessel and ex-vessel dosimeters.With the aim to enlarge the in-house validation database of the LWR neutron fluence assessments for the Swiss reactors, an MCNPX-based analysis of this benchmark was recently performed, using the general-purpose point-wise library JEFF-3.1. The analysis was done in compliance with the benchmark specifications and using the same or similar assumptions/approximations as employed by the previous participants in order to ensure consistency in the comparison of solutions.A detailed assessment of different libraries was not performed in these past calculations because of the rather poor statistical precision achieved at that time when modeling the high-energy reactions with MCNPX. In the course of recent additional optimization studies the variances of the calculation results have been significantly reduced, allowing thereby comparing the performance of different neutron data libraries for the analysis of this benchmark. This comparison is presented in this paper and includes an assessment of the data libraries JEFF-3.1, JEFF-3.1.1, ENDF/B-VII.0 and IRDF-2002. The differences observed in the results and their potential sources are discussed.
A. Dokhane,A. Vasiliev,M. Hursin,D. Rochman,H. Ferroukhi 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.5
The aim of this paper is to assess the reliability and accuracy of the PSI standard method, used in manyprevious works, for the quantification of ND uncertainties in the SPERT-III RIA transient, by quantifyingthe discrepancy between the actual inserted reactivity and the original static reactivity worth and theirassociated uncertainties. The assessment has shown that the inherent S3K neutron source renormalization scheme, introduced before starting the transient, alters the original static reactivity worth of thetransient CR and reduces the associated uncertainty due to the ND perturbation. In order to overcomethese limitations, two additional methods have been developed based on CR adjustment. The comparative study performed between the three methods has showed clearly the high sensitivity of the obtained results to the selected approach and pointed out the importance of using the right procedure inorder to simulate correctly the effect of ND uncertainties on the overall parameters in a RIA transient. This study has proven that the approach that allows matching the original static reactivity worth andstarting the transient from criticality is the most reliable method since it conservatively preserves theeffect of the ND uncertainties on the inserted reactivity during a RIA transient.