Finite element analysis of the 2240 MW HTGR PCRV
Technical Report
·
OSTI ID:5508384
Three-dimensional finite element calculations for the response of the prestressed concrete reactor vessel for the 2240 MW HTGR which evaluated the stress distributions and concentrations were accomplished. Constitutive equations utilized in this evaluation were linear elastic, Von Mises elastic-plastic and the empirical Kotsovos-Newman concrete fit with and without steel reinforcing. Ultimate values of the internal pressures without initial prestress were obtained. Also stresses in the annular concrete retaining cover over the stream generator were evaluated.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5508384
- Report Number(s):
- NUREG/CR-4526; LA-10663-MS; ON: TI86010876
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
BUILDING MATERIALS
CONCRETES
CONTAINERS
FINITE ELEMENT METHOD
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
NUMERICAL SOLUTION
PRESTRESSED CONCRETE
REACTOR VESSELS
REACTORS
STRESS ANALYSIS
THREE-DIMENSIONAL CALCULATIONS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
BUILDING MATERIALS
CONCRETES
CONTAINERS
FINITE ELEMENT METHOD
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
NUMERICAL SOLUTION
PRESTRESSED CONCRETE
REACTOR VESSELS
REACTORS
STRESS ANALYSIS
THREE-DIMENSIONAL CALCULATIONS