This specification covers finished pellets composed of sintered uranium-plutonium dioxide for fast reactor fuel. Specimens shall be sampled and tested suitably, and shall conform accordingly to chemical (uranium and plutonium content, impurity content, stoichiometry, moisture, gas content, and americium-241 content), nuclear (isotopic content, and equivalent plutonium at a given date), and physical (dimensions, density, grain size an pore morphology, homogeneity, particle size and distribution, integrity, surface cracks, circumferential chips, pellet ends, cleanliness and workmanship, and identification) requirements.
This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.
1.1 This specification is for finished sintered (uranium-plutonium) dioxide pellets. It applies to (uranium-plutonium) dioxide pellets containing plutonium additions in the range from 10 to 40 weight % and uranium of any 235U content. The isotopic composition of the plutonium component will be as normally produced by in-reactor neutron irradiation of uranium having less than 5 % 235U or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.
1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50 — Domestic Licensing of Production and Utilization Facilities; Title 10, Part 71 — Packaging and Transportation of Radioactive Material; and Title 49, Part 173 — General Requirements for Shipments and Packaging.
1.3 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: 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 (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C757 Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
C859 Terminology Relating to Nuclear Materials
C1165 Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode
C1204 Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration
C1206 Test Method for Plutonium by Iron (II)/Chromium (VI) Amperometric Titration
E105 Practice for Probability Sampling of Materials
ANSI/ASMENQA-1 Quality Assurance Program Requirements for Nuclear Facility Applications
U.S. Government Documents
U.S.NuclearRegulator Packaging and Transportation of Radioactive Material
breeder reactor; fast reactor; mixed oxide fuels; nuclear fuel; nuclear fuel pellets; plutonium; uranium; Breeder reactor core components; Mixed oxides (MOX); Nuclear fuels (reactor)--specifications; Nuclear materials/applications--specifications; Nuclear reactor vessels; Plutonium; Uranium--specifications; Uranium-plutonium dioxide pellets (sintered) ;
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
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