ASTM-E669 Master Matrix for Nuclear Fuel Cycle Standards (Withdrawn 2000)

ASTM-E669 - 1991 EDITION - SUPERSEDED
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Master Matrix for Nuclear Fuel Cycle Standards (Withdrawn 2000)

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)

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Document Number

ASTM-E669-91

Revision Level

1991 EDITION

Status

Superseded

Modification Type

Withdrawn

Publication Date

May 15, 1991

Document Type

Classification

Page Count

3 pages

Committee Number

C26.91