| << 40-Zr-92 | 40-Zr-93 | 40-Zr-94 >> |
| << 40-Zr-92 MT107 (n,α) | MT102 (n,γ) or MT5 (Zr94 production) | 40-Zr-94 MT1 (n,total) >> |
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| Node | Settings | Display |
|---|---|---|
| NEA / Incident neutron data | ||
| EXFOR / Cross sections / Zr93 / (,G)40-ZR-94 | ||
| BROND-3.1 / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| CENDL-3.2 / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| EAF-2010 / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| ENDF/B-VIII.0 / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| JEFF-3.3 / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| JENDL-4.0u / Cross sections / Zr93 / MT=102 : (z,γ) / Cross section | ||
| TENDL-2019 / Energy-angle distributions / Zr93 / MT=5 : (z,anything) / MF3+MF6MT5 |