Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0

Thanh Mai Vu, Donny Hartanto, Thoi Nam Chu, Nhu Viet Ha Pham, Thi Hong Bui

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

The reliability of eigenvalue and kinetic parameter calculation results for CERCER and CERMET fueled ADS was investigated by conducting sensitivity and uncertainty analysis by SERPENT 2 and ENDF/B-VIII.0 library. The total error of keff of CERCER core was found to be 1268.7 pcm and larger than that of CERMET one (609.4 pcm). It mostly comes from cross section uncertainty of 237Np (n,g) – the biggest contributor, 239Pu (n,f), 232Th (n,g) and 237Np (n,f). Therefore, the accuracy of nuclear data of those isotopes is recommended to be improved to achieve more reliable eigenvalue results. For kinetic parameters, the uncertainty of evaluated results mainly originated from the 237Np (n,g), 239Pu (n,inl) and 23Na (n,ela) cross sections. Nevertheless, its impact on simulation accuracy is not significant (less than 1%). Thus, ENDF/B-VIII.0 nuclear data is sufficient to evaluate βeff, leff, and λeff and discuss the safety features of ADS.

Original languageEnglish
Article number108912
JournalAnnals of Nuclear Energy
Volume168
DOIs
StatePublished - Apr 2022
Externally publishedYes

Funding

This research is funded by the Vietnam National University , Hanoi (VNU), under project number QG.20.20.

FundersFunder number
VNUQG.20.20
Đại học Quốc gia Hà Nội

    Keywords

    • ADS
    • ENDF/B-VIII.0
    • Eigenvalue
    • Kinetic parameters
    • NJOY
    • SERPENT 2
    • Sensitivity
    • Uncertainty

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