Standard Specification for Uranium Hexafluoride Enriched to Less Than 5% 235U1

SCOPE
1.1 This specification applies to nuclear grade uranium hexafluoride, (UF6), that has been processed through an enrichment plant to obtain uranium of any  235 U concentration below 5% and that is intended for fuel fabrication. The scope of the standard includes specifications for UF6 enriched from Commercial Natural UF6, and UF6 enriched from Reprocessed UF6. Both Commercial Natural and Reprocessed UF6 are defined in Section 3. The objectives of this specification are two-fold: ( ) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that with respect to fuel design and manufacture the product is essentially equivalent to enriched product made from natural UF6, and ( ) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and protect the employees, process equipment, and the environment.
1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 which is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, parties concerned may agree to other appropriate conditions.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or any other way of using UF6. (See, for example, TID-7016, DP-532 and DOE-5633.3.)
1.4 Cylinders used for transport of Enriched Reprocessed UF6 shall not be used for Enriched Commercial Grade UF6 unless decontaminated internally before filling with Enriched Commercial Grade UF6.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

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Status
Historical
Publication Date
31-Dec-1995
Current Stage
Ref Project

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ASTM C996-96 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5% 235U1
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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Please contact ASTM International (www.astm.org) for the latest information.
Designation: C 996 – 96
Standard Specification for
235
1
Uranium Hexafluoride Enriched to Less Than 5 % U
This standard is issued under the fixed designation C 996; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope state, and local regulations for processing, shipping, or in any
other way using UF (see, for example, TID-7016, DP-532,
6
1.1 This specification covers nuclear grade uranium
ORNL-NUREG-CSD-6, and DOE 5633.3B).
hexafluoride (UF ) that either has been processed through an
6
1.4 The values stated in SI units are to be regarded as the
enrichment plant, or has been produced by the blending of
standard. The values given in parentheses are for information
Highly Enriched Uranium with other uranium to obtain ura-
235
only.
nium of any U concentration below 5 % and that is intended
for fuel fabrication. The scope of this specification includes
2. Referenced Documents
specifications for UF enriched from Commercial Natural UF ,
6 6
2.1 ASTM Standards:
and UF enriched from Reprocessed UF ; enriched UF
6 6 6
C 761 Test Methods for Chemical, Mass Spectrometric,
derived from Highly Enriched Uranium is included in the
Spectrochemical, Nuclear, and Radiochemical Analysis of
specification for UF enriched from Commercial Natural
6
2
Uranium Hexafluoride
UF (see Note 1). Commercial Natural UF , Reprocessed UF ,
6 6 6
C 787 Specification for Uranium Hexafluoride for Enrich-
HighlyEnrichedUF ,andDerivedEnrichedUF aredefinedin
6 6
2
ment
Section 3. The objectives of this specification are twofold: (1)
2
C 859 Terminology Relating to Nuclear Materials
To define the impurity and uranium isotope limits for Enriched
C 1052 Practice for Bulk Sampling of Liquid Uranium
Commercial Grade UF so that, with respect to fuel design and
6
2
Hexafluoride
manufacture, it is essentially equivalent to enriched uranium
C 1295 Test Method for Gamma Energy Emission from
made from natural UF ; and (2) To define limits for Enriched
6
2
Fission Products in Uranium Hexafluoride
Reprocessed UF to be expected if Reprocessed UF is to be
6 6
3
2.2 ANSI Standards:
enriched without dilution with Commercial Natural UF . For
6
ANSI-ASME NQA-1 Quality Assurance Program Require-
such UF , special provisions, not defined herein, may be
6
ments for Nuclear Facilities
needed to ensure fuel performance and to protect the work
ANSI N14.1 Packaging of Uranium Hexafluoride forTrans-
force, process equipment, and the environment.
port
NOTE 1—Due to limited experience with enriched UF derived from
6
2.3 U.S. Government Documents:
Highly Enriched Uranium, such material must be carefully monitored to
Inspection, Weighing, and Sampling of Uranium Hexafluo-
ensure compliance with this specification; when such Derived Enriched
ride Cylinders, Procedure for Handling and Analysis of
UF is directly provided to the buyer, it shall be identified as such by the
6
Uranium Hexafluoride, Vol. 1, DOE Report ORO-671-1,
seller.
4
latest revision
1.2 This specification is intended to provide the nuclear
Uranium Hexafluoride: A Manual of Good Handling Prac-
industry with a standard for enriched UF that is to be used in
6
tices, United States Enrichment Corporation Report
the production of sinterable UO powder for fuel fabrication.
2 5
USEC-651, latest revision
In addition to this specification, the parties concerned may
Nuclear Safety Guide, U.S. NRC Report TID-7016, Rev. 2,
agree to other appropriate conditions.
4
1978, and ORNL-NUREG-CSD-6
1.3 The scope of this specification does not comprehen-
Clarke, H. K., Handbook of Nuclear Safety, DOE Report
sively cover all provisions for preventing criticality accidents
4
DP-532
or requirements for health and safety or for shipping. Obser-
Code of Federal Regulations, Title 10, Part 50, (Appendix
vance of this specification does not relieve the user of the
4
B)
obligation to conform to all applicable international, federal,
2
Annual Book of ASTM Standards, Vol 12.01.
3
Available from theAmerican National Standards Institute, 11W. 42nd St., 13th
1
This specification is under the jurisdiction of ASTM Committee C-26 on Floor, New York, NY 10036.
4
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Available from the Superintendent of Documents, U.S. Government Printing
and Fertile Material Specifications. Office, Washington, DC 20402.
5
Current edition approved July 10, 1996. Published September 1996. Originally Available from United States Enrichment Corporation, 6903 Rockledge Drive,
published as C 996 – 83. Last previous edition C 996 – 90. Bethesda, MD 20817.
Copyright © ASTM International, 100 Barr Harbor Dr
...

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