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A plot showing the number of evaluated (ENDF) isotopes versus time

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Number of materials in nuclear data evaluations in ENDF format

Number of materials in nuclear evaluations in ENDF format

The term "material" refers either to a single isotope, or a mixture of isotopes: a natural element, a molecule, an alloy, lumped fission products, etc.

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A plot showing the number of evaluated (ENDF) isotopes versus time

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