Assessment of long-term structural behavior of an asymmetric multi-cavity PCRV. [900 MW(e)]

Conference · Sun Feb 01 04:00:00 EST 1981

OSTI ID:6214751

Cheung, K. C.; Koploy, M.

Recent design development of the prestressed concrete reactor vessels (PCRVS) for HTGR systems incorporates an asymmetric arrangement of major cavities with the center of the core cavity offset from the geometric center of the vessel. This layout allows a more effective utilization of space. This paper presents the results of an analytical investigation of the creep effects of an asymmetric, off-set core PCRV configuraton using the finite element method. The finite element model was based on the proposed PCRV for a 900-MW(e) steam cycle HTGR. Results indicate that the long-term behavior of an offset core PCRV does not depart significantly from that of a symmetric arrangement.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76ET35301
• OSTI ID: 6214751
• Report Number(s): GA-A-16269; CONF-810801-11
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
BUILDING MATERIALS
CONCRETES
CONTAINERS
CREEP
FINITE ELEMENT METHOD
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
PRESTRESSED CONCRETE
REACTOR VESSELS
REACTORS