ASTM C757-16e1

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.

General Information

• Status: Historical
• Publication Date: 31-Mar-2016
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.02 - Fuel and Fertile Material Specifications

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
´1
Designation:C757 −16
Standard Specification 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.
1
ε NOTE—Editorially corrected 6.4 in October 2016.
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
prepared by in-reactor neutron irradiation of natural or slightly safety concerns, if any, associated with its use. It is the
enriched uranium or by in-reactor neutron irradiation of responsibility of the user of this standard to establish appro-
recycled plutonium mixed with uranium. priate safety and health practices and determine the applica-
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
discussed. Observance of this specification does not relieve the
2.1 ASTM Standards:
user of the obligation to be aware of and conform to all
B243 Terminology of Powder Metallurgy
applicable international, national, or federal, state, and local
C697 Test Methods for Chemical, Mass Spectrometric, and
regulations pertaining to possessing, shipping, processing, or
Spectrochemical Analysis of Nuclear-Grade Plutonium
using source or special nuclear material. For examples in the
Dioxide Powders and Pellets
U.S. Government, relevant documents are Code of Federal
C859 Terminology Relating to Nuclear Materials
Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic
C1233 Practice for Determining Equivalent Boron Contents
2
Energy Commission Report TID-7016 , and “Handbook of
of Nuclear Materials
Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commis-
C1274 Test Method forAdvanced Ceramic Specific Surface
2
sion Report, DP-532 .
Area by Physical Adsorption
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
E105 Practice for Probability Sampling of Materials
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 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/C0757-16E01. contact ASTM Customer Service at [e-mail]. 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

---------------------- Page: 1 ----------------------
´1
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
...

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 − 16 C757 − 16
Standard Specification 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.
1
ε NOTE—Editorially corrected 6.4 in October 2016.
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
be applicable for a particular Mixed Oxide (MOX, that is (U, Pu)O ) fuel pellet manufacturing process
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
1.1 This specification covers nuclear grade PuO powder. It applies to PuO of various isotopic compositions as normally
2 2
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
2 2
TID-7016 , and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission 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
C859 Terminology Relating to Nuclear Materials
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
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.
ɛ1
Current edition approved April 1, 2016. Published April 2016. Originally approved in 1974. Last previous edition approved in 2011 as C757 – 06 (2011) . DOI:
10.1520/C0757-16.10.1520/C0757-16E01.
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 [e-mail]. 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 ----------------------
´1
C757 − 16
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 Hexafluoride and Uranyl Nitrate
Solution
C1770 Test Method for Determination of Loose and Tapped Bulk Density of Plutonium Oxide
E105 Practice for Probability Sampling of Materials
2.2 ASME Standard:
4
ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications
2.3 U.S. Government Documents:
2
Code of Federal Regulations, Title 10, Nuclear Safety Guide, U.S. At
...