ASTM C833
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets
| Organization: | ASTM |
| Publication Date: | 10 September 1995 |
| Status: | inactive |
| Page Count: | 4 |
| ICS Code (Fissile materials and nuclear fuel technology): | 27.120.30 |
scope:
1. Scope
1.1 This specification covers finished sintered (uranium-plutonium) dioxide pellets. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 10 % weight. The isotopic composition of the diluent uranium shall be of any 235U composition. The isotopic composition of the plutonium component shall be as normally prepared by in-reactor neutron irradiation of uranium having less than 5 % 235U.
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 international, federal, state, and local regulations on possessing, shipping, processing, or using source or special nuclear materials. Guidance is provided in CFR Title 10, TID-7016, and DP-532 (see 2.3).
1.3 All terms used herein are as defined in Terminology C 859.
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
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