Applications of high-strength concrete to the development of the prestressed concrete reactor vessel (PCRV) design for an HTGR-SC/C plant

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6378779

Naus, D J

The PCRV research and development program at ORNL consists of generic studies to provide technical support for ongoing PCRV-related studies, to contribute to the technological data base, and to provide independent review and evaluation of the relevant technology. Recent activities under this program have concentrated on the development of high-strength concrete mix designs for the PCRV of a 2240 MW(t) HTGR-SC/C plant, and the testing of models to both evaluate the behavior of high-strength concretes (plain and fibrous) and to develop model testing techniques. A test program to develop and evaluate high-strength (greater than or equal to 63.4 MPa) concretes utilizing materials from four sources which are in close proximity to potential sites for an HTGR plant is currently under way. The program consists of three phases. Phase I involves an evaluation of the cement, fly ash, admixtures and aggregate materials relative to their capability to produce concretes having the desired strength properties. Phase II is concerned with the evaluation of the effects of elevated temperatures (less than or equal to 316/sup 0/C) on the strength properties of mixes selected for detailed evaluation. Phase III involves a determination of the creep characteristics and thermal properties of the selected mixes. An overview of each of these phases is presented as well as results obtained to date under Phase I which is approximately 75% completed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6378779
• Report Number(s): CONF-841252-1; ON: DE85005093
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
AEROSOL WASTES
ASHES
BUILDING MATERIALS
CONCRETES
CONTAINERS
CREEP
DESIGN
DISPERSIONS
EVALUATION
FLY ASH
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MIXTURES
PRESTRESSED CONCRETE
REACTOR MATERIALS
REACTOR VESSELS
REACTORS
REINFORCED CONCRETE
REINFORCED MATERIALS
RESIDUES
TESTING
ULTIMATE STRENGTH
WASTES