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ASTM C833-23
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
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STANDARD published on 1.6.2023
The information about the standard:
Designation standards: ASTM C833-23
Publication date standards: 1.6.2023
SKU: NS-1149770
The number of pages: 5
Approximate weight : 15 g (0.03 lbs)
Country: American technical standard
Category: Technical standards ASTM
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Annotation of standard text ASTM C833-23 :
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
Keywords:
light water reactors, mixed oxide fuel, nuclear fuel, plutonium, plutonium disposition, thermal reactors, uranium-plutonium oxide,, ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
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