ASTM International - ASTM C1008-99(2008)
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets—Fast Reactor Fuel (Withdrawn 2014)
|Publication Date:||1 January 2008|
|ICS Code (Fissile materials and nuclear fuel technology):||27.120.30|
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.
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... View More
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.View Less
Pellets—Fast Reactor Fuel (Withdrawn 2014)