| MT | Reaction | 0.0253-eV | Maxwellian Average  | 
    g-factor | Resonance Integral  | 
    14-MeV | Fiss. Spec. Average  | 
   
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 143.3 (b) | 145.5 (b) | 1.015 | − | 6.181 (b) | 7.542 (b) | 
| 2 | (n,elastic) | 12.43 (b) | 14.03 (b) | 1.129 | − | 3.121 (b) | 5.216 (b) | 
| 4 | (n,inelastic) | ( E-thr = 50.43 keV ) | 591.1 (mb) | 2.155 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.172 MeV ) | 1.381 (b) | 67.55 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.92 MeV ) | 1.032 (b) | 137.0 (μb) | |||
| 18 | (n,fission) | 700.3 (mb) | 700.7 (mb) | 1.001 | 1.023 (b) | 55.70 (mb) | 55.70 (mb) | 
| 37 | (n,4n) | ( E-thr = 17.32 MeV ) | − | 257.6 (nb) | |||
| 102 | (n,γ) | 130.1 (b) | 130.1 (b) | 1.001 | 435.7 (b) | 3.735 (μb) | 45.26 (mb) | 
| 456 | νp | 1.266 | − | − | − | 2.991 | − | 
| 455 | νd | 1.716e-2 | − | − | − | 1.118e-2 | − | 
| 
      These cross sections are calculated from JENDL-4.0 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 :
      
     
 
      νp,
      νd
      : numbers of prompt and delayed neutrons per fission.
      
      |