ASTM C1008-99(2008) - 1.1.2008
 
1. Scope

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

C859-26

Standard Terminology Relating to Nuclear Materials

C1206-02

Standard Test Method for Plutonium by Iron (II)/Chromium (VI) Amperometric Titration

C1204-14(2023)

Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

C1165-23

Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

C757-16(2021)

Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors

C753-16a(2021)

Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder (Includes all amendments and changes 10/22/2021).

C698-24

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)

U.S. Nuclear Regulatory Commission, Title 10, Part 71,

Packaging and Transportation of Radioactive Material

ANSI/ASME NQA-1

Quality Assurance Program Requirements for Nuclear Facility Applications

E105-21

Standard Guide for Probability Sampling of Materials