A Summary Description of Design Criteria, Codes, Standards, and Regulatory Provisions Typically Used for the Civil and Structural Design of Nuclear Fuel Cycle Facilities

XXYYZZ,; Nuclear Fuel Cycle Committee of the Committee on Nuclear Structures and Materials of the Structural Division of ASCE,

A Summary Description of Design Criteria, Codes, Standards, and Regulatory Provisions Typically Used for the Civil and Structural Design of Nuclear Fuel Cycle Facilities

by
Nuclear Fuel Cycle Committee of the Committee on Nuclear Structures and Materials of the Structural Division of ASCE

American Society of Civil Engineers, New York, NY
978-0-87262-651-5 (ISBN-13) | 0-87262-651-2 (ISBN-10), 1988, Soft Cover, Pg. 113

Out of Print: Not available at ASCE Bookstore.

Document Type: Book

Abstract:

A summary of design criteria, codes, standards, and regulatory provisions applicable to the civil and structural design of the eight principal facilities of the nuclear fuel cycle are presented including uranium mines and mills, uranium conversion, uranium enrichment, nuclear fuel fabrication, fuel handling at nuclear power generating plants, independent spent fuel storage, nuclear fuel reprocessing plants, and nuclear waste disposal. This information is intended to provide guidance and give direction on government regulations and industry codes and standards to the designer of a new facility as it assembles and lists information on the requirements of the design from several different sources. Illustrations are presented tracing the flow of fuel from mining to final repository through two paths. The first is the once-through fuel cycle which involves no reprocessing and is the most prevalent today in the U.S., and the second is the uranium-only recycle fuel cycle in which the fuel is reprocessed and the fissionable material reused for fresh fuel assemblies.

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