The ACI-ASME code for concrete reactor vessels and containments (USA)

This paper presents highlights of the new ASME Section III, Division 2, Code for Concrete Reactor Vessels (CRV) and Containments, along with some comparisons with the contents of related, yet totally dissimilar, documents available in the United Kingdom, France, and Germany. The Division 2 Code covers the total aspects of the work associated with a CRV or containment, from planning stages through proof testing. Requirements of the Nuclear Regulatory Commission (NRC) and State Jurisdictional Authorities are included. Administrative control, inspection enforcement, and technical criteria are set forth. The Code has drawn its support from the involvement of a wide segment of the nuclear community including national and state governments, technical societies, universities, designers, constructors, fabricators, owner/operators, material suppliers, consultants, insurance agencies, and various service groups. (author)