| << 96-Cm-244 | 96-Cm-245 | 96-Cm-246 >> |
| << MT1 (n,total) | MT18 (n,fission) | MT102 (n,γ) >> |
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| Node | Settings | Display |
|---|---|---|
| NEA / Incident neutron data | ||
| EXFOR / Cross sections / Cm245 / (,F) | ||
| 10121.028 | ||
| 10128.004 | ||
| 10165.002 | ||
| 10730.005 | ||
| 13993.003 | ||
| 13994.002 | ||
| 22941.039 | ||
| 22941.040 | ||
| 23115.002 | ||
| 23120.002 | ||
| 23168.003 | ||
| 23186.004 | ||
| 40467.020 | ||
| 41023.002 | ||
| 41023.003 | ||
| 41108.002 | ||
| 41180.004 | ||
| 41303.007 | ||
| 41303.009 | ||
| 41336.013 | ||
| 41359.002 | ||
| 41360.002 | ||
| 41369.028 | ||
| V1002.669.2 | ||
| BROND-3.1 / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section | ||
| EAF-2010 / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section | ||
| ENDF/B-VIII.0 / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section | ||
| JEFF-3.3 / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section | ||
| JENDL-4.0u / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section | ||
| TENDL-2019 / Cross sections / Cm245 / MT=18 : (z,fission) / Cross section |