Analytical investigation of multicavity prestressed concrete pressure vessels for elastic loading conditions. [HTGR]
A three-dimensional finite-element analysis of a commercial high-temperature gas-cooled reactor (HTGR) was made using the finite-element code STATIC-SAP. Four loading conditions were analyzed elastically to evaluate the behavior of the concentric core prestressed concrete reactor vessel (PCRV) of the HTGR. The results of the analysis were evaluated in accordance with Section III, Division 2, of the ASME Code for Reactor Vessels and Containments. The calculated maximum stresses were found to be well within the Code-allowable values. The analysis was preceded by an evaluation of candidate computer codes using comparisons of experimental data with analytical results for the Ohbayashi-Gumi multicavity PCRV model. This vessel was chosen as a basis for comparison because of its geometrical similarity to the large multicavity PCRV and the anticipated availability of a complete set of the original experimental data. The three-dimensional finite-element codes NONSAP and STATIC-SAP were used for the analysis of the Ohbayashi-Gumi vessel.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6591974
- Report Number(s):
- ORNL/TM-6099; TRN: 79-001060
- Country of Publication:
- United States
- Language:
- English
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HTGR TYPE REACTORS
PRESSURE VESSELS
STRESS ANALYSIS
FINITE ELEMENT METHOD
PRESTRESSED CONCRETE
BUILDING MATERIALS
CONCRETES
CONTAINERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MATERIALS
NUMERICAL SOLUTION
REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated