ASTM C1008-99

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets-Fast Reactor Fuel

SCOPE
1.1 These test methods cover procedures for testing rigid electrical insulation normally manufactured in flat sheet or plate form. They are generally used as terminal boards, spacers, voltage barriers, and circuit boards.
Note 1—For tests applying to vulcanized fiber reference should be made to Test Methods D 619. Note 2—This standard resembles IEC 60893-2, Specification for Rigid Industrial Laminated Sheets Based On Thermosetting Resins for Electrical Purpose, Methods of Tests.
1.2 The test methods appear in the following sections:TestSectionsASTM Test MethodAcetone extractable matter 83 to 84D 494Arc resistance47 D 495Ash56 to 60 ...Bonding strength49 to 54...Burning rate and flame resistance61 to 75...Compressive strength25 D 695Conditioning4 D 6054Dissipation factor34 to 40D 669Dielectric strength28 to 33D 149Expansion (linear thermal)76D 696Flexural properties12 to 24D 790Hardness (Rockwell)55 D 785Insulation resistance and resistivity41 to 46D 257Permittivity34 to 40D 150Resistance to impact26 D 256Tensile properties7 to 11D 638Thickness5 to 6D 374Tracking resistance48 D 2132Warp or twist77 to 82...Water absorption27 D 570
1.3 The values stated in inch-pound units are to be regarded as the standard. The metric equivalents of inch-pound units given in these test methods may be approximate.
1.4 This is a fire-test-response standard. See Sections 61 through 75, which are the procedures for burning rate and flame resistance.
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. Specific precautionary statements are given in 31.1 and 61.5.

General Information

• Status: Historical
• Publication Date: 09-Jan-1999
• 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

Relations

• Referred By: ASTM C1411-20 - Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis
• Effective Date: 10-Jan-1999
• Referred By: ASTM C1816-16 - Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
• Effective Date: 10-Jan-1999
• Referred By: ASTM C1871-22 - Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer
• Effective Date: 10-Jan-1999
• Referred By: ASTM C1625-19 - Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
• Effective Date: 10-Jan-1999
• Referred By: ASTM C1672-17 - Standard Test Method for Determination of Uranium or Plutonium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer
• Effective Date: 10-Jan-1999
• Referred By: ASTM C1832-23 - Standard Test Method for Determination of Uranium Isotopic Composition by Modified Total Evaporation (MTE) Method Using Thermal Ionization Mass Spectrometer
• Effective Date: 10-Jan-1999

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
Designation: C 1008 – 99
Standard Specification for
Sintered (Uranium-Plutonium) Dioxide
1
Pellets—Fast Reactor Fuel
This standard is issued under the fixed designation C 1008; 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
(uranium-plutonium) dioxide pellets for fast reactor use. It recognizes the diversity of manufacturing
methods by which (uranium-plutonium) dioxide pellets are produced and the many special
requirements for chemical and physical characterization which may be imposed by the operating
conditions to which the pellets will be subjected in specific reactor systems. It does not recognize the
possible problems associated with the reprocessing of such pellets. It is therefore anticipated that the
buyer may supplement this specification with additional requirements for specific applications.
1. Scope of the user of this standard to establish appropriate safety and
health practices and determine the applicability of regulatory
1.1 This specification is for finished sintered (uranium-
limitations prior to use.
plutonium) dioxide pellets. It applies to (uranium-plutonium)
dioxide pellets containing plutonium additions in the range
2. Referenced Documents
235
from 10 to 40 weight % and uranium of any U content. The
2.1 ASTM Standards:
isotopic composition of the plutonium component will be as
C 698 Test Methods for Chemical, Mass Spectrometric, and
normallyproducedbyin-reactorneutronirradiationofuranium
235
SpectrochemicalAnalysis of Nuclear-Grade Mixed Oxides
having less than 5 % U or by in-reactor neutron irradiation
2
((U, Pu)O )
2
of recycled plutonium mixed with uranium.
C 753 Specification for Nuclear-Grade, Sinterable Uranium
1.2 This specification does not include (1) provisions for
2
Dioxide Powder
preventing criticality accidents or (2) requirements for health
C 757 Specification for Nuclear-Grade Plutonium Dioxide
andsafety.Observanceofthisspecificationdoesnotrelievethe
2
Powder, Sinterable
user of the obligation to be aware of and conform to all
2
C 859 Terminology Relating to Nuclear Materials
applicable international, federal, state, and local regulations
C 1165 Test Method for Determining Plutonium by
pertaining to possessing, processing, shipping, or using source
Controlled-Potential Coulometry in H SO at a Platinum
2 4
or special nuclear material. Examples of U.S. government
2
Working Electrode
documentsareCodeofFederalRegulationsTitle10,Part50—
C 1204 Test Method for Uranium in the Presence of Pluto-
Domestic Licensing of Production and Utilization Facilities;
nium by Iron (II) Reduction in Phosphoric Acid Followed
Title 10, Part 71 — Packaging and Transportation of Radioac-
2
by Chromium (VI) Titration
tive Material; and Title 49, Part 173 — General Requirements
C 1206 Test Method for Plutonium by Iron (II)/Chromium
for Shipments and Packaging.
2
(VI) Amperometric Titration
1.3 The following safety hazards caveat pertains only to the
3
E 105 Practice for Probability Sampling of Materials
technical requirements portion, Section 4, of this specification:
2.2 ANSI Standard:
This standard does not purport to address all of the safety
ANSI/ASME NQA-1 Quality Assurance Program Require-
concerns, if any, associated with its use. It is the responsibility
4
ments for Nuclear Facility Applications
1
This specification is under the jurisdiction of ASTM Committee C-26 on
2
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Annual Book of ASTM Standards, Vol 12.01.
3
and Fertile Material Specifications. Annual Book of ASTM Standards, Vol 14.02.
4
Current edition approved Jan. 10, 1999. Published March 1999. Originally Available from American National Standards Institute, 11 W. 42nd St., 13th
published as C 1008 – 84. Last previous edition C 1008 – 92. Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C 1008
2.3 U.S. Government Documents: 4.1.3 Stoichiometry— The oxygen-to-heavy-metal ratio of
Code of Federal Regulations, Title 10, (Energy) Part 50, sinteredfuelpelletsshallbewithintherangefrom1.94to2.01.
Domestic Licensing of Production and Utilization Facili- The nominal value and allowable tolerances shall be agreed
5
ties (10 CFR 50) upon between the buyer and the seller.
U.S.DepartmentofTransportation,Title49, Transportation,
4.1.4 Moisture Content— The moisture content shall not
Chapter 1, Materials Transporta
...