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Spent fuel characterization analysis using various nuclear data libraries

Nuclear Engineering and Technology, 2022, 54(9), , pp.3260-3271 [Peer Reviewed Journal]

2022 Korean Nuclear Society ;ISSN: 1738-5733 ;EISSN: 2234-358X ;DOI: 10.1016/j.net.2022.04.009

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  • Title:
    Spent fuel characterization analysis using various nuclear data libraries
  • Author: Čalič, Dušan ; Kromar, Marjan
  • Subjects: Decay heat ; Monte Carlo ; Nuclide uncertainties ; Serpent ; Spent nuclear fuel ; 원자력공학
  • Is Part Of: Nuclear Engineering and Technology, 2022, 54(9), , pp.3260-3271
  • Description: Experience shows that the solution to waste management in any national programme is lengthy and burdened with uncertainties. There are several uncertainties that contribute to the costs associated with spent fuel management. In this work, we have analysed the impact of the current nuclear data on the isotopic composition of the spent fuel and consequently their influence on the main spent fuel observables such as decay heat, activity, neutron multiplication factor, and neutron and photon source terms. Nuclear libraries based on the most general nuclear data ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0 and JEFF-3.3 are considered. A typical NPP Krško fuel assembly is analysed using the Monte Carlo code Serpent 2. The analysis considers burnup of up to 60 GWd/tU and cooling times of up to 100 years. The comparison of results showed significant differences, which should be taken into account when selecting the library and evaluating the uncertainty in determining the characteristics of the spent fuel.
  • Publisher: Elsevier B.V
  • Language: English;Korean
  • Identifier: ISSN: 1738-5733
    EISSN: 2234-358X
    DOI: 10.1016/j.net.2022.04.009
  • Source: Alma/SFX Local Collection
    DOAJ Directory of Open Access Journals
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