Document Center is acquired by Nimonik

Scope

1.1 The purpose of this standard is to present a master-matrix approach for the identification and classification of areas in the nuclear fuel cycle in which the development of standards will be needed.

1.2 The master matrix is defined as the array of operations and activities included in the fuel cycle for nuclear reactors. These operations start with the mining, milling, and fuel fabrication, continue with the transportation of spent fuel after discharge from a reactor, and culminate with the shipment of waste to a repository, of refabricated fuel to a reactor station, and of recycled uranium to an enrichment plant (see Fig. 1). Matrix standards dealing specifically with nuclear reactors is the function of other groups as established in Section 10 of Recommended Guide E584.

Keywords

Cycling; Matrix data/programs; Nuclear fuels (reactor); master matrix for nuclear fuel cycle standards; ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

To find similar documents by ASTM Volume:

12.01 (Nuclear Energy (I))

To find similar documents by classification:

27.120.30 (Fissile materials and nuclear fuel technology Including raw materials Radioactive wastes, see 13.030.30)

This document comes with our free Notification Service, good for the life of the document.

This document is available in Paper format.