ACI ACI 349.1R-07

ACI 349.1R-07 PDF Download

Standard EN Sample
ACI 349.1R-07 Sample

Reinforced Concrete Design for Thermal Effects on Nuclear Power Plant Structures

SKU147864644 Published by American Concrete Institute ACI Publication Date2007-01-01 Pages CountPages40

ACI 349.1R-07 is a standard that provides a design-oriented approach for considering thermal effects on reinforced concrete structures, with a specific focus on nuclear power plant structures. The standard aims to conform to the general provisions of Appendix E of ACI 349, but it can also be applied to other types of structures.

The report discusses the general behavior of structures under thermal effects and highlights the significant issues to consider in reinforcement design. It specifically addresses two types of structures: frames and axisymmetric shells.

For frame structures, the standard describes a rationale for determining the extent of component cracking, which is important for determining the cracked structure thermal forces and moments. It provides stiffness coefficients and carryover factors in graphical form, based on the extent of component cracking and the reinforcement ratio. The standard also presents fixed-end thermal moments for cracked components, considering both temperature gradient across the depth of the component and end displacements due to a uniform temperature change along adjacent components.

For axisymmetric shells, the standard presents normalized cracked section thermal moments in graphical form. These moments are normalized with respect to the cross-sectional dimensions and the temperature gradient across the section. They are presented as a function of the internal axial forces and moments acting on the section and the reinforcement ratio.

The use of the graphical information provided in the standard is illustrated through examples, which help designers in applying the thermal effects design approach to their specific projects.

Details
Descriptorscracking (fracturing); frames; nuclear power plants; shells; structural analysis; structural design; temperature; thermal effect; thermal gradient; thermal properties
ICS Codes27.120.20 - Nuclear power plants. Safety
Language(s)English
ISBN97808703124605
File Size4.0 MB
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