| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 296614 | Nuclear Engineering and Design | 2014 | 5 Pages |
In nuclear power plant construction, both Safety-Related and Non-Safety-Related structures are present. Safety-Related RC structures will generally include Concrete Containment and other Category I (CAT I) structures. The reinforcement development/splice length for reinforcement in containment structures is provided according to ASME SECTION III Div 2 (ACI 359-07) Code. The development and splice length requirements for other Safety-Related CAT I RC Structures are given in ACI 349-06, Code requirements for Nuclear Safety-Related Concrete Structures. The development and splice length requirements for Non-Safety structures are given in ACI 318-08.Unfortunately, the requirements in the three Codes (ACI 359, ACI 349 and ACI 318) are not the same and can vary significantly. This results, for example, in the same bar size requiring different development/splice lengths for different structures which is extra work for the fabricator and also increases the potential for confusion/mix up at a particular job site.This evaluates and discusses the differences in development and splice length requirements in the above-mentioned Codes for CAT I and Non-Safety-Related structures and explores opportunities for harmonization of requirements among the three Codes, where possible and appropriate. The development and splice length requirement for higher grade reinforcement (Gr 75 and Gr 80), which are expected to be allowed in the next editions of the US nuclear codes will also be discussed. Based on this study, some recommendations are made to streamline the development/splice requirements to help improve construction of New Gen nuclear construction.
