ASTM-C1008:2008 Edition

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C1008-99(2008) Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pelletsâ€”Fast Reactor Fuel

Published By	Publication Date	Number of Pages
ASTM	2008	4

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Categories: 27.120.30 - Fissile materials and nuclear fuel technology, ASTM

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Description

ASTM C1008-99-Reapproved2008

Withdrawn Standard: Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets—Fast Reactor Fuel (Withdrawn 2014)

ASTM C1008

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.

Keywords

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 Code

ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

DOI: 10.1520/C1008-99R08

PDF Catalog

PDF Pages	PDF Title
1	Scope Referenced Documents
2	Terminology Technical Requirements TABLE 1
3	Lot Requirements Sampling Testing and Certification Packaging and Shipping
4	Quality Assurance Keywords A1. DENSITY DETERMINATION A1.1 A1.2

Additional information

Standard Title	C1008-99(2008) Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pelletsâ€”Fast Reactor Fuel
Published Code	ASTM
Publication Date	2008
Pages Count	4
ICS Codes	27.120.30 - Fissile materials and nuclear fuel technology