1. Scope

1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C 967).

1.2 These practices also provide for obtaeining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C 1022).

1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.

1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR, 10, Chapter 1.)

1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

1.6 This standard does not purport to address all of the safety problems, 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.

2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

ASTM Standards

C967 Specification for Uranium Ore Concentrate

C1022 Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

Keywords

sampling; UOC; uranium ore; uranium-ore concentrate; Falling stream method; Natural moisture method; Nuclear fuels (reactor); Reciprocating cutter method; Sampling nuclear/related energy sources; Specimen preparation (for testing)--nuclear applications; Uranium; Uranium ore; Vacuum seals/sealing; Vezzin method; Auger sampling method; Calcination methods; Concrete tanks;

ICS Code

ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

DOI: 10.1520/C1075-93R04

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