ASTM C1008 - 99(2008) en

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

45,11 54,58 Incl BTW

Over deze norm

Status Definitief
Aantal pagina's 4
Gepubliceerd op 01-01-2008
Taal Engels

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.


ICS-code 27.120.30
Engelse titel Standard Specification for Sintered (Uranium-Plutonium) Dioxide
PelletsFast Reactor Fuel



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