scope:

This Code provides minimum requirements for design and construction of nuclear safety-related concrete structures and structural members for nuclear facilities. Safety-related structures and structural members subject to this Code are those concrete structures that support, house, or protect nuclear safety class systems or component parts of nuclear safety class systems.

Specifically excluded from this Code are those structures covered by "Code for Concrete Containments," ASME Boiler and Pressure Vessel Code Section III, Division 2, and pertinent General Requirements (ACI 359).

This Code includes design and loading conditions that are unique to nuclear facilities, including shear design under biaxial tension conditions, consideration of thermal and seismic effects, and impact and impulsive loads.

For structural concrete, f_c′ shall not be less than 3000 psi, unless otherwise specified.

This Code shall govern in all matters pertaining to design and construction of reinforced concrete structures, as defined in 1.1.1, except wherever this Code is in conflict with the specific provisions of the authority having jurisdiction (AHJ).

Same as ACI 318-08.

Same as ACI 318-08, except the last sentence "See also Section 22.1.3."

Concrete on steel deck

Same as ACI 318-08.

This Code does not govern the design of structural concrete slabs cast on stay-in-place, composite steel form deck. Concrete used in the construction of such slabs shall be governed by Chapters 1 through 6 of this Code, where applicable. Portions of such slabs designed as reinforced concrete are governed by this Code.

Special provisions for earthquake resistance- Provisions of Chapter 21 shall be satisfied (see Section 21.1.1).

This Code, along with relevant sections of ACI 350, governs design and construction of tanks and reservoirs (non-lined) associated with safety-related nuclear structures.

The American Concrete Institute "Code Requirements for Nuclear Safety-Related Concrete Structures (ACI 349-13)," called the Code, provides minimum requirements for reinforced concrete design or construction in applications where protection against potential radioactive releases is a concern. The scope of the Code provides requirements for the analysis, design, construction, testing, and evaluation of new and existing concrete nuclear structures. While the requirements of this Code pertain primarily to new concrete structures, corresponding recommendations for the evaluation of existing concrete nuclear structures are provided in ACI 349.3R.^1.1 Some special structures involve unique problems that are not covered by the Code, such as structures that function as leakage barriers to contain the effects of the loss of coolant accident. The owner is to identify nuclear safety-related structures and establish which of them are covered by "Code for Concrete Containments (ACI 359)"^1.2 and its latest revisions instead of this Code. The Code is applicable to radioactive waste repository structures; however, considerations of thermal loads, load combinations, and long-term durability should be considered.

In general, the Code requirements are based on test results from concrete specimens having a compressive strength of 6000 psi or less. Although no maximum concrete compressive strength is specified, the applicability of various requirements and formulations should be verified when concrete compressive strengths are higher than 6000 psi.

Minimum compressive concrete strength has been established as 3000 psi to be consistent with the seismic provisions of Chapter 21 of ACI 349-13 and ACI 318.

Intentionally left blank, as this Code does not deal with residential structures.

This Code addresses piles, piers, and caissons in Section 21.12.4.

The provisions of this Code apply to slabs-on-ground. In addition to the requirements of this Code, the licensed design professional should consider other issues, as outlined in ACI 360R^1.3 and PTI's Design of Post-Tensioned Slabs-on-Ground.^1.4

Refer to Section R21.1.1 for details.

ACI 349-13 provision is applied to the spent fuel pool pit and refueling canal as well as other safety-related tanks. In addition, detailed recommendations given in "Code Requirements for Environmental Engineering Concrete Structures and Commentary" reported by ACI Committee 350 should be followed for nonlined tanks and reservoirs associated with safety-related nuclear structures. In case of a conflict, the more restrictive provision of ACI 349 or ACI 350 should be followed.