ASTM International - ASTM C1346-96

Standard Practice for Dissolution of UF6 from P-10 Tubes

historical
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Organization: ASTM International
Publication Date: 10 January 2002
Status: historical
Page Count: 3
ICS Code (Fissile materials and nuclear fuel technology): 27.120.30
scope:

1.1 This practice covers the dissolution of UF 6 from a P-10 tube to provide solutions for analysis.

1.2 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. For specific safeguard and safety precaution statements, see Section 8.

Document History

February 1, 2019
Standard Practice for Dissolution of UF6 from P-10 Tubes
1.1 This practice covers the dissolution of UF6 from a P-10 tube to provide solutions for analysis. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement...
January 1, 2014
Standard Practice for Dissolution of UF6 from P-10 Tubes
1.1 This practice covers the dissolution of UF6 from a P-10 tube to provide solutions for analysis. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement...
June 1, 2008
Standard Practice for Dissolution of UF6 from P-10 Tubes
1.1 This practice covers the dissolution of UF6 from a P-10 tube to provide solutions for analysis. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement...
ASTM C1346-96
January 10, 2002
Standard Practice for Dissolution of UF6 from P-10 Tubes
1.1 This practice covers the dissolution of UF 6 from a P-10 tube to provide solutions for analysis. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with...
January 10, 2002
Standard Practice for Dissolution of UF6 from P-10 Tubes
Uranium hexafluoride is a basic material used to prepare nuclear reactor fuel. To be suitable for this purpose the material must meet criteria for uranium content, isotopic composition, metallic...
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