Development of high-strength concrete mix designs in support of the prestressed concrete reactor vessel design for a HTGR steam cycle/cogeneration plant

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5418018

Naus, D J; Oland, C B

Design optimization studies indicate that a significant reduction in the size of the PCRV for a 2240 MW(t) HTGR plant can be effected through utilization of high-strength concrete in conjunction with large capacity prestressing systems. A three-phase test program to develop and evaluate high-strength concretes (>63.4 MPa) is described. Results obtained under Phase I of the investigation related to materials selection-evaluation and mix design development are presented. 3 refs., 4 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5418018
• Report Number(s): CONF-850809-75; ON: DE85016310
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
AEROSOL WASTES
ASHES
BUILDING MATERIALS
CEMENTS
CONCRETES
CONTAINERS
CREEP
DESIGN
FLY ASH
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
OPTIMIZATION
PORTLAND CEMENT
PRESTRESSED CONCRETE
REACTOR VESSELS
REACTORS
RESIDUES
WASTES