Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation
This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel reprocessing plant under the free drop impact of spent fuel cask (SFC) and fuel assembly (FA) during the on-site transportation. At the present Part I of this paper, the large-scale SFC model free dro...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2021-08-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321000942 |
| _version_ | 1818436897002749952 |
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| author | Z.C. Li Y.H. Yang Z.F. Dong T. Huang H. Wu |
| author_facet | Z.C. Li Y.H. Yang Z.F. Dong T. Huang H. Wu |
| author_sort | Z.C. Li |
| collection | DOAJ |
| description | This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel reprocessing plant under the free drop impact of spent fuel cask (SFC) and fuel assembly (FA) during the on-site transportation. At the present Part I of this paper, the large-scale SFC model free drop test and the corresponding numerical simulations are performed. Firstly, a composite target which is composed of the protective structure, i.e., a thin RC plate (representing the inverted U-shaped slab in the loading shaft) and/or an autoclaved aerated concrete (AAC) blocks sacrificial layer, as well as a thick RC plate (representing the bottom slab in the loading shaft) is designed and fabricated. Then, based on the large dropping tower, the free drop test of large-scale SFC model with the mass of 3 t is carried out from the height of 7 m–11 m. It indicates that the bottom slab in the loading shaft could not resist the free drop impact of SFC. The composite protective structure can effectively reduce the damage and vibrations of the bottom slab, and the inverted U-shaped slab could relieve the damage of the AAC blocks layer dramatically. Furthermore, based on the finite element (FE) program LS-DYNA, the corresponding refined numerical simulations are performed. By comparing the experimental and numerical damage and vibration accelerations of the composite structures, the present adopted numerical algorithms, constitutive models and parameters are validated, which will be applied in the further assessment of drop impact effects of full-scale SFC and FA on prototype nuclear fuel reprocessing plant in the next Part II of this paper. |
| first_indexed | 2024-12-14T17:16:04Z |
| format | Article |
| id | doaj.art-f46bd87736694ed8942b1a634db408ff |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-14T17:16:04Z |
| publishDate | 2021-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-f46bd87736694ed8942b1a634db408ff2022-12-21T22:53:26ZengElsevierNuclear Engineering and Technology1738-57332021-08-0153826822695Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validationZ.C. Li0Y.H. Yang1Z.F. Dong2T. Huang3H. Wu4State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd, Shenzhen, Guangdong, 518172, China; China Nuclear Power Design Co., Ltd, Shenzhen, Guangdong, 518172, ChinaCollege of Civil Engineering, Tongji University, Shanghai, 200092, ChinaState Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd, Shenzhen, Guangdong, 518172, China; China Nuclear Power Design Co., Ltd, Shenzhen, Guangdong, 518172, ChinaState Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd, Shenzhen, Guangdong, 518172, China; China Nuclear Power Design Co., Ltd, Shenzhen, Guangdong, 518172, ChinaCollege of Civil Engineering, Tongji University, Shanghai, 200092, China; Corresponding author.This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel reprocessing plant under the free drop impact of spent fuel cask (SFC) and fuel assembly (FA) during the on-site transportation. At the present Part I of this paper, the large-scale SFC model free drop test and the corresponding numerical simulations are performed. Firstly, a composite target which is composed of the protective structure, i.e., a thin RC plate (representing the inverted U-shaped slab in the loading shaft) and/or an autoclaved aerated concrete (AAC) blocks sacrificial layer, as well as a thick RC plate (representing the bottom slab in the loading shaft) is designed and fabricated. Then, based on the large dropping tower, the free drop test of large-scale SFC model with the mass of 3 t is carried out from the height of 7 m–11 m. It indicates that the bottom slab in the loading shaft could not resist the free drop impact of SFC. The composite protective structure can effectively reduce the damage and vibrations of the bottom slab, and the inverted U-shaped slab could relieve the damage of the AAC blocks layer dramatically. Furthermore, based on the finite element (FE) program LS-DYNA, the corresponding refined numerical simulations are performed. By comparing the experimental and numerical damage and vibration accelerations of the composite structures, the present adopted numerical algorithms, constitutive models and parameters are validated, which will be applied in the further assessment of drop impact effects of full-scale SFC and FA on prototype nuclear fuel reprocessing plant in the next Part II of this paper.http://www.sciencedirect.com/science/article/pii/S1738573321000942Spent fuel caskFree dropNuclear fuel reprocessing plantAutoclaved aerated concreteNumerical simulation |
| spellingShingle | Z.C. Li Y.H. Yang Z.F. Dong T. Huang H. Wu Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation Nuclear Engineering and Technology Spent fuel cask Free drop Nuclear fuel reprocessing plant Autoclaved aerated concrete Numerical simulation |
| title | Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation |
| title_full | Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation |
| title_fullStr | Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation |
| title_full_unstemmed | Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation |
| title_short | Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation |
| title_sort | safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part i large scale model test and finite element model validation |
| topic | Spent fuel cask Free drop Nuclear fuel reprocessing plant Autoclaved aerated concrete Numerical simulation |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321000942 |
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