ASTM C757-16
(Specification)Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 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 applicable international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322.
1.3 The PuO2 shall be produced by 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:C757 −16
StandardSpecification for
Nuclear-Grade Plutonium Dioxide Powder for Light Water
1
Reactors
This standard is issued under the fixed designation C757; 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.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general standard for plutonium
dioxide (PuO ) powder. It recognizes the diversity of manufacturing methods by which PuO powders
2 2
are produced and the many special requirements for chemical and physical characterization that may
beapplicableforaparticularMixedOxide(MOX,thatis(U,Pu)O )fuelpelletmanufacturingprocess
2
or imposed by the end user of the powder in different light water reactors. It is, therefore, anticipated
that the buyer 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 PuO powder. It
2
applies to PuO of various isotopic compositions as normally 1.5 This standard does not purport to address all of the
2
safety concerns, if any, associated with its use. It is the
prepared by in-reactor neutron irradiation of natural or slightly
enriched uranium or by in-reactor neutron irradiation of responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
recycled plutonium mixed with uranium.
bility of regulatory limitations prior to use.
1.2 There is no discussion of or provision for preventing
criticality incidents, nor are health and safety requirements, the
2. Referenced Documents
avoidance of hazards, or shipping precautions and controls
3
2.1 ASTM Standards:
discussed. Observance of this specification does not relieve the
B243 Terminology of Powder Metallurgy
user of the obligation to be aware of and conform to all
C697 Test Methods for Chemical, Mass Spectrometric, and
applicable international, national, or federal, state, and local
Spectrochemical Analysis of Nuclear-Grade Plutonium
regulations pertaining to possessing, shipping, processing, or
Dioxide Powders and Pellets
using source or special nuclear material. For examples in the
C859 Terminology Relating to Nuclear Materials
U.S. Government, relevant documents are Code of Federal
C1233 Practice for Determining Equivalent Boron Contents
Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic
2
of Nuclear Materials
Energy Commission Report TID-7016 , and “Handbook of
C1274 Test Method forAdvanced Ceramic Specific Surface
Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commis-
2
Area by Physical Adsorption
sion Report, DP-532 .
C1295 Test Method for Gamma Energy Emission from
1.3 The PuO shall be produced by a qualified process and
2
Fission and Decay Products in Uranium Hexafluoride and
in accordance with a quality assurance program approved by
Uranyl Nitrate Solution
the user.
C1770 Test Method for Determination of Loose and Tapped
Bulk Density of Plutonium Oxide
1
This specification is under the jurisdiction of ASTM Committee C26 on
E105 Practice for Probability Sampling of Materials
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel
and Fertile Material Specifications.
Current edition approved April 1, 2016. Published April 2016. Originally
ɛ1 3
approved in 1974. Last previous edition approved in 2011 as C757 – 06 (2011) . For referenced ASTM standards, visit the ASTM website, www.astm.org, or
DOI: 10.1520/C0757-16. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
Available from Superintendent of Documents, U.S. Government Printing Standards volume information, refer to the standard’s Document Summary page on
Office, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20402. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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C757−16
TABLE 1 Impurity Elements and Maximum Concentration Limits
2.2 ASME Standard:
ASME NQA-1 QualityAssurance Requirements for Nuclear Maximum Concentration
C
4
Element Limit
Facility Applications
of Plutonium, µg/gPu
2.3 U.S. Government Documents:
Aluminum (Al) 300
Code of Federal Regulations, Title 10, Nuclear Safety
Boron (B) 3
Cadmium (Cd) 3
Guide, U.S. Atomic Energy Commission Report TID-
A
2
Carbon (C) 500
7016
Chlorine (Cl) 300
“Handbook of Nuclear Safety,” Clark, H. K., U.S. Atomic
Chromium (Cr) 200
2
Energy Commission Report, DP-532 Dysprosium (Dy) 0.5
Europium (Eu) 0.
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´1
Designation: C757 − 06 (Reapproved 2011) C757 − 16
Standard Specification for
Nuclear-Grade Plutonium Dioxide Powder, SinterablePowder
1
for Light Water Reactors
This standard is issued under the fixed designation C757; 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
ε NOTE—Section 4.6 was changed editorially in June 2011.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general standard for sinterable
plutonium dioxide (PuO ) powder. It recognizes the diversity of manufacturing methods by which
2
plutoniumPuO dioxide powders are produced,produced and the many special requirements for
2
chemical and physical characterization that may be applicable for a particular Mixed Oxide (MOX,
that is (U, Pu)O ) fuel pellet manufacturing process or imposed by the end useuser of the powder in
2
a specific reactor system.different light water reactors. It is, therefore, anticipated that the buyer may
supplement this specification with more stringent or additional requirements for specific applications.
1. Scope
1.1 This specification covers nuclear grade plutoniumPuO dioxide, sinterable powder obtained by the oxalate precipitation
2
route, calcined above 500°C, or any other equivalent process acceptable to thepowder. It applies to PuO buyer. Included is
2
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 national applicable international, national, or federal, state, and local regulations
on processing, shipping, pertaining to possessing, shipping, processing, or using source or special nuclear materials.material. For
examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S.
2
Atomic Energy Commission Report TID-7016 , and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission
2
Report, DP-532 .
1.3 The PuO shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.
2
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.
2. Referenced Documents
3
2.1 ASTM Standards:
B243 Terminology of Powder Metallurgy
C697 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide
Powders and Pellets
1
This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and Fertile
Material Specifications.
Current edition approved June 1, 2011April 1, 2016. Published July 2011April 2016. Originally approved in 1974. Last previous edition approved in 20062011 as
ɛ1
C757 – 06.C757 – 06 (2011) . DOI: 10.1520/C0757-06R11E01.10.1520/C0757-16.
2
Available from Superintendent of Documents, U.S. Government Printing Office, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20402.
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C757 − 16
C859 Terminology Relating to Nuclear Materials
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
C1274 Test Method for Advanced Ceramic Specific Surface Area by Physical Adsorption
C1295 Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium He
...
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