ASTM International - ASTM C970-87(1997)

Standard Practice for Sampling Special Nuclear Materials in Multi-Container Lots

historical
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Organization: ASTM International
Publication Date: 1 January 1997
Status: historical
Page Count: 7
ICS Code (Fissile materials and nuclear fuel technology): 27.120.30
scope:

1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample.

1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans.

1.3 The values stated in SI units are to be regarded as the standard.

1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Document History

January 1, 2006
Standard Practice for Sampling Special Nuclear Materials in Multi-Container Lots (Withdrawn 2012)
1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of...
ASTM C970-87(1997)
January 1, 1997
Standard Practice for Sampling Special Nuclear Materials in Multi-Container Lots
1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of...
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