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ASTM International - ASTM E669-91

Master Matrix for Nuclear Fuel Cycle Standards (Withdrawn 2000)

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Organization: ASTM International
Publication Date: 1 January 1991
Status: inactive
Page Count: 3
ICS Code (Fissile materials and nuclear fuel technology): 27.120.30
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.

Document History

ASTM E669-91
January 1, 1991
Master Matrix for Nuclear Fuel Cycle Standards (Withdrawn 2000)
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...
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