Fluid-structure-interaction Analyses of Reactor Vessel Using Improved Hybrid Lagrangian Eulerian Code ALICE-II PDF Download
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Author: C. Y. Wang
Publisher:
ISBN:
Category :
Languages : en
Pages : 38
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Book Description
Author: C. Y. Wang
Publisher:
ISBN:
Category :
Languages : en
Pages : 38
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 38
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Book Description
This paper describes fluid-structure-interaction and structure response analyses of a reactor vessel subjected to loadings associated with postulated accidents, using the hybrid Lagrangian-Eulerian code ALICE-II. This code has been improved recently to accommodate many features associated with innovative designs of reactor vessels. Calculational capabilities have been developed to treat water in the reactor cavity outside the vessel, internal shield structures and internal thin shells. The objective of the present analyses is to study the cover response and potential for missile generation in response to a fuel-coolant interaction in the core region. Three calculations were performed using the cover weight as a parameter. To study the effect of the cavity water, vessel response calculations for both wet- and dry-cavity designs are compared. Results indicate that for all cases studied and for the design parameters assumed, the calculated cover displacements are all smaller than the bolts' ultimate displacement and no missile generation of the closure head is predicted. Also, solutions reveal that the cavity water of the wet-cavity design plays an important role of restraining the downward displacement of the bottom head. Based on these studies, the analyses predict that the structure integrity is maintained throughout the postulated accident for the wet-cavity design.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7
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Book Description
This paper describes fluid-structure-interaction and structure response analyses of a reactor vessel subjected to loadings associated with postulated accidents, using the improved hybrid Lagrangian-Eulerian code ALICE-II. The objective of the present analyses is to study the cover response and potential for missile generation in response to a fuel-coolant interaction in the core region. Three calculations were performed using the cover weight as a parameter. To study the effect of the cavity water outside the reactor vessel, vessel response calculations for both wet- and dry-cavity designs are compared. Results indicate that for all cases studied and for the design parameters assumed, the calculated cover displacements are all smaller than the bolts' ultimate displacement and no missile generation of the closure head is predicted. Also, solutions reveal that the cavity water of the wet-cavity design plays an important role of restraining the downward displacement of the bottom head. Based on these studies, the analyses predict that the structure integrity is maintained throughout the postulated accident for the wet-cavity design.
Author: Han Y. Chu
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 58
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Author: C. Y. Wang
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 216
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Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 892
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Author:
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ISBN:
Category : Power resources
Languages : en
Pages : 922
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![Recent Developments of the Arbitrary Lagrangian-Eulerian Containment Code ALICE-II. [LMFBR]. PDF](https://books.google.com/books/content/images/frontcover/0rGnAQAACAAJ?fife=w80-h100)
Author:
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Category :
Languages : en
Pages :
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The ANL arbitrary Lagrangian Eulerian containment code ALICE was developed for use in fast reactor containment studies and is particularly suited for problems involving complex fluid-structure interactions. Many improvements have been made which has resulted in a second version of the code, ALICE-II. A selection of some important improvements are given in this paper. To realistically analyze the above-core hydrodynamics containing a movable upper internal structure (UIS), a 3-D pipe element has been adopted to calculate the response of the UIS columns that connect the UIS to the vessel head. A corotational coordinate scheme for large displacement, small strain, elastic-plastic structural-dynamic analysis is utilized in the formulation. Both geometric and material nonlinearities are considered. The governing equations are integrated explicitly using a central difference procedure. Many sample problems are presented, including comparisons of ALICE-II and ICECO-CEL results on the APRICOT Phase 3 problems.
Author:
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ISBN:
Category : Science
Languages : en
Pages : 732
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 540
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