Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor
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 (Kawad...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
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Elsevier
2021-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321003399 |
| _version_ | 1818721463768711168 |
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| author | Kenichi Kawada Tohru Suzuki |
| author_facet | Kenichi Kawada Tohru Suzuki |
| author_sort | Kenichi Kawada |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-12-17T20:39:08Z |
| format | Article |
| id | doaj.art-6118bf437168400fb1e8b4aea57e6bed |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-17T20:39:08Z |
| publishDate | 2021-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-6118bf437168400fb1e8b4aea57e6bed2022-12-21T21:33:22ZengElsevierNuclear Engineering and Technology1738-57332021-12-01531239303943Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactorKenichi Kawada0Tohru Suzuki1Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency, Ibaraki, Japan; Corresponding author.Department of Nuclear Safety Engineering, Tokyo City University, Tokyo, JapanTo 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.http://www.sciencedirect.com/science/article/pii/S1738573321003399FBRCDASAS4AULOFCABRISevere accident |
| spellingShingle | Kenichi Kawada Tohru Suzuki Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor Nuclear Engineering and Technology FBR CDA SAS4A ULOF CABRI Severe accident |
| title | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor |
| title_full | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor |
| title_fullStr | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor |
| title_full_unstemmed | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor |
| title_short | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor |
| title_sort | development and validation of fuel stub motion model for the disrupted core of a sodium cooled fast reactor |
| topic | FBR CDA SAS4A ULOF CABRI Severe accident |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321003399 |
| work_keys_str_mv | AT kenichikawada developmentandvalidationoffuelstubmotionmodelforthedisruptedcoreofasodiumcooledfastreactor AT tohrusuzuki developmentandvalidationoffuelstubmotionmodelforthedisruptedcoreofasodiumcooledfastreactor |