ASTM C757-90(2002)
(Specification)Standard Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
Standard Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
SCOPE
1.1 This specification covers nuclear grade plutonium dioxide, sinterable powder obtained by the oxalate precipitation route, calcined above 500°C, or any other equivalent process acceptable to the purchaser. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural- or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.
1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all Federal, state, and local regulations on processing, shipping, or using source or special nuclear materials. Examples of U.S. Government documents are N7.2 Radiation Protection in Nuclear Reactor Fuel Fabrication Plants, Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-7016, and "Handbook of Nuclear Safety", H. K. Clark, U.S. Atomic Energy Commission Report, DP-532.
1.3 The PuO2 shall be produced by the processor employing a qualified process and in accordance with a quality assurance program approved by the user.
1.4 The values stated in SI units are to be regarded as the standard.
1.5 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.
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Designation: C 757 – 90 (Reapproved 2002)
Standard Specification for
Nuclear-Grade Plutonium Dioxide Powder, Sinterable
This standard is issued under the fixed designation C 757; 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 (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general standard for sinterable
plutonium dioxide powder. It recognizes the diversity of manufacturing methods by which plutonium
dioxide powders are produced, and the many special requirements for chemical and physical
characterization that may be imposed by the end use of the powder in a specific reactor system. It is,
therefore, anticipated that the purchaser may supplement this specification with more stringent or
additional requirements for specific applications.
1. Scope 1.4 The values stated in SI units are to be regarded as the
standard.
1.1 This specification covers nuclear grade plutonium diox-
1.5 This standard does not purport to address all of the
ide, sinterable powder obtained by the oxalate precipitation
safety concerns, if any, associated with its use. It is the
route, calcined above 500°C, or any other equivalent process
responsibility of the user of this standard to establish appro-
acceptable to the purchaser. Included is plutonium dioxide of
priate safety and health practices and determine the applica-
various isotopic compositions as normally prepared by in-
bility of regulatory limitations prior to use.
reactor neutron irradiation of natural- or slightly enriched
uranium or by in-reactor neutron irradiation of recycled pluto-
2. Referenced Documents
nium mixed with uranium.
2.1 ASTM Standards:
1.2 There is no discussion of or provision for preventing
C 697 Test Method for Chemical, Mass Spectrometric, and
criticality incidents, nor are health and safety requirements, the
Spectrochemical Analysis of Nuclear-Grade Plutonium
avoidance of hazards, or shipping precautions and controls
Dioxide Powders and Pellets
discussed. Observance of this specification does not relieve the
2.2 ANSI Standards:
user of the obligation to be aware of and conform to all
N7.2 Radiation Protection in Nuclear Reactor Fuel Fabrica-
Federal, state, and local regulations on processing, shipping, or
tion Plants
using source or special nuclear materials. Examples of U.S.
ANSI–ASME NQA-1 QualityAssurance Program Require-
Government documents are N7.2 Radiation Protection in
2 ments for Nuclear Facilities
Nuclear Reactor Fuel Fabrication Plants , Code of Federal
2.3 U.S. Government Documents:
Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic
3 Code of Federal Regulations, Title 10, Nuclear Safety
Energy Commission Report TID-7016 , and “Handbook of
Guide, U.S. Atomic Energy Commission Report TID-
Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commis-
3 7016
sion Report, DP-532 .
“ Handbook of Nuclear Safety,” Clark, H. K., U.S.Atomic
1.3 The PuO shall be produced by the processor employing
Energy Commission Report, DP-532
a qualified process and in accordance with a quality assurance
2.4 ISO Standard:
program approved by the user.
ISO8300 DeterminationofPucontentinplutoniumdioxide
(PuO ) of Nuclear Grade Quality, Gravimetric Method
This specification is under the jurisdiction of ASTM Committee C26 on
3. Isotopic Content
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel
and Fertile Material Specifications.
3.1 Concentrations and homogeneity ranges of the pluto-
Current edition approved Oct. 26, 1990. Published February 1991. Originally
nium isotopes shall be as specified by the purchaser.
published as C 757 – 74. Last previous edition C 757 – 83.
Available from American National Standards Institute, 11 W. 42nd St., 13th
Floor, New York, NY 10036.
Available from Superintendent of Documents, U.S. Government Printing
Office, Washington, DC 20402. Annual Book of ASTM Standards, Vol 12.01.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 757
3.2 The isotopic composition of the final product shall be mined on any one lot shall not exceed the surface area
determined by mass spectrometry and shall be reported on a determined on any of the other lots by more than a factor of
weight basis. two.
6. Sampling
4. Chemical Composition
6.1 Plutonium oxide is hygroscopic and can absorb suffi-
4.1 The necessary chemical analyses shall be performed on
cient water during exposure to a moist atmosphere to cause
portions of a representative sample taken in accordance with
detectable analytical errors. Sampling, weighing of the sample,
the Sampling section after sampling within an agreed period.
and handling the sample shall be done under atmospheric
Analytical results shall be reported on a plutonium basis.
conditions that do not alter the moisture or impurity content, or
4.1.1 The uranium content of the plutonium dioxide shall be
both, of the sample.
measured and reported.
6.2 A representative sample of powder shall be taken from
4.1.2 The thorium content of the plutonium dioxide shall
each lot.
not exceed 200 µg/g of plutonium.
6.2.1 A lot is defined as the quantity of material that is
4.1.3 The americium content shall be measured and re-
uniform in isotopic, chemical, and physical characteristics.
ported. The maximum acceptable americium content shall be
...
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