uranium-236
Sign in to saveAlso known as U-236, 236U, Uranium 236
Uranium-236 (U or U-236) is an isotope of uranium that is neither fissile with thermal neutrons, nor very good fertile material, but is generally considered a nuisance and long-lived radioactive waste. It is found in spent nuclear fuel and in the reprocessed uranium made from spent nuclear fuel.
Key facts
- Isotope.mass_number
- 236
- Isotope.symbol
- U
- Isotope.num_neutrons
- 144
- Isotope.num_protons
- 92
- Isotope.abundance
- 10-11 to 10−10
- Isotope.decay_product
- Thorium-232
- Isotope.decay_mass
- 232
- Isotope.decay_symbol
- Th
- Isotope.parent
- Protactinium-236
- Isotope.parent_mass
- 236
- Isotope.parent_symbol
- Pa
- Isotope.parent2
- Neptunium-236
- Isotope.parent2_mass
- 236
- Isotope.parent2_symbol
- Np
- Isotope.parent3
- Plutonium-240
- Isotope.parent3_mass
- 240
- Isotope.parent3_symbol
- Pu
- Isotope.mass
- 236.045566
via Wikipedia infobox
Wikidata facts
- Mass
- 236.045566201
Show 9 more facts
- atomic number
- 92
- neutron number
- 144
- half-life
- 23420000.0
- spin quantum number
- 0.0
- parity quantum number
- 1
- mass excess
- 42444.644
- binding energy
- 1790410.224
- canonical SMILES
- [236U]
- chemical formula
- U
via Wikidata · CC0
~6 min read
Article
8 sectionsContents
- Creation and yield
- Destruction and decay
- Difficulty of separation
- Contribution to radioactivity of reprocessed uranium
- Depleted uranium
- See also
- References
- External links
Uranium-236 (U or U-236) is an isotope of uranium that is neither fissile with thermal neutrons, nor very good fertile material, but is generally considered a nuisance and long-lived radioactive waste. It is found in spent nuclear fuel and in the reprocessed uranium made from spent nuclear fuel.
==Creation and yield== The fissile isotope uranium-235 fuels most nuclear reactors. When U absorbs a thermal neutron, one of two processes can occur. About 85.5% of the time, it will fission; about 14.5% of the time, it will not fission, instead emitting gamma radiation and yielding U. Thus, the yield of U per U+n reaction is about 14.5%, and the yield of fission products is about 85.5%. In comparison, the yields of the most abundant individual fission products like caesium-137, strontium-90, and technetium-99 are between 6% and 7%, and the combined yield of medium-lived (10 years and up) and long-lived fission products is about 32%, or a few percent less as some are transmuted by neutron capture.
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