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neutron number of spontaneous fission

Input interpretation

spontaneous fission | neutron number
spontaneous fission | neutron number

Summary

median | 157 highest | 176 (Mc-291) lowest | 138 (Cm-234 and U-230) distribution |
median | 157 highest | 176 (Mc-291) lowest | 138 (Cm-234 and U-230) distribution |

Distribution plots

Random Queries

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