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http://dx.doi.org/10.1016/j.net.2021.06.018

Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor  

Kawada, Kenichi (Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency)
Suzuki, Tohru (Department of Nuclear Safety Engineering, Tokyo City University)
Publication Information
Nuclear Engineering and Technology / v.53, no.12, 2021 , pp. 3930-3943 More about this Journal
Abstract
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive accidents for MOX-fueled Sodium-cooled Fast Reactors (SFRs), the authors have investigated in detail the physical phenomena under unprotected loss-of-flow (ULOF) conditions in a previous paper (Kawada and Suzuki, 2020) [1]. As the conclusion of the last article, fuel stub motion, in which the residual fuel pellets would move toward the core central region after fuel pin disruption, was identified as one of the key phenomena to be appropriately simulated for the initiating phase of ULOF. In the present paper, based on the analysis of the experimental data, the behaviors related to the stub motion were evaluated and quantified by the author from scratch. A simple model describing fuel stub motion, which was not modeled in the previous SAS4A code, was newly proposed. The applicability of the proposed model was validated through a series of analyses for the CABRI experiments, by which the stub motion would be represented with reasonable conservativeness for the reactivity evaluation of disrupted core.
Keywords
FBR; CDA; SAS4A; ULOF; CABRI; Severe accident;
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Times Cited By KSCI : 1  (Citation Analysis)
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