| MT | Reaction | 0.0253-eV | Maxwellian Average | g-factor | Resonance Integral | 14-MeV | Fiss. Spec. Average | 
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 9.072 (b) | 10.02 (b) | 1.104 | − | 5.215 (b) | 6.729 (b) | 
| 2 | (n,elastic) | 7.373 (b) | 8.320 (b) | 1.128 | − | 2.538 (b) | 4.253 (b) | 
| 4 | (n,inelastic) | ( E-thr = 111.8 keV ) | 490.3 (mb) | 2.433 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.452 MeV ) | 2.181 (b) | 5.649 (mb) | |||
| 17 | (n,3n) | ( E-thr = 13.68 MeV ) | 1.688 (mb) | 7.149 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 364.6 (nb) | 25.52 (μb) | 21.24 (nb) | 
| 28 | (n,np) | ( E-thr = 7.739 MeV ) | 10.16 (μb) | 12.18 (nb) | |||
| 102 | (n,γ) | 1.698 (b) | 1.698 (b) | 1.000 | 16.22 (b) | 1.000 (mb) | 37.00 (mb) | 
| 103 | (n,p) | ( E-thr = 2.260 MeV ) | 2.044 (mb) | 642.4 (nb) | |||
| 104 | (n,d) | ( E-thr = 5.503 MeV ) | 248.2 (μb) | 58.39 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 8.670 (μb) | 720.7 (μb) | 796.5 (nb) | 
| These cross sections are calculated from JENDL-3.3 at 300K. The background color of each cell noted a cross section means the order of the cross-section value. The unit of cross section, (b), means barns, and SI prefixes are used as following. (kb) → 103(b),   (mb) → 10−3(b),
           (μb) → 10−6(b),  (nb) → 10−9(b). MT is a number that defines a reaction type. For the relation between MT and reaction type, please see  here  or refer to the manual of ENDF formats. 
      Maxwellian Average :
      
 
      where T denotes the temperature, and kB the Boltzmann constant.
      The upper and lower limits of integration, EL and EU
      are set to 10−5 eV and 10 eV, respectively.
      
      Resonance Integral :
      
 
      with  EL = 0.5 eV  and  EU = 10 MeV.
      
      U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
      
 
      with  EL = 10−5 eV  and  EU = 20 MeV.
      The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
      
      Westcott g-factor :
      
 |