ASTM C1297-03
Historical Standard: ASTM C1297-03 Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials
SUPERSEDED (see Active link, below)
ASTM C1297
1. Scope
1.1 This guide covers the qualification of analysts to perform chemical analysis or physical measurements of nuclear fuel cycle materials. The guidance is general in that it is applicable to all analytical methods, but must be applied method by method. Also, the guidance is general in that it may be applied to initial qualification or requalification.
1.2 The guidance is provided in the following sections:
Section | |
Qualification Considerations | 4 |
Demonstration Process | 5 |
Statistical Tests | 6 |
1.3 This standard does not apply to maintaining qualification during routine use of a method. Maintaining qualification is included in Guide C 1210.
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.
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
C1009 Guide for Establishing a Quality Assurance Program for Analytical Chemistry Laboratories Within the Nuclear Industry
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
C1128 Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials
C1156 Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials
C1210 Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within the Nuclear Industry
C1215 Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in the Nuclear Industry
ISO Standard
ISOGuide30 Terms and Definitions Used in Connection with Reference Materials Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.Keywords
analyst qualification; measurement(s); quality assurance; reference materials; Laboratory--nuclear; Nuclear applications/materials; Nuclear facilities; Nuclear fuels (reactor); Qualifications--nuclear facilities;
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1297-03
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