| MT | Reaction | 0.0253-eV | Maxwellian Average  | 
    g-factor | Resonance Integral  | 
    14-MeV | Fiss. Spec. Average  | 
   
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 8.096 (b) | 8.802 (b) | 1.087 | − | 4.072 (b) | 5.840 (b) | 
| 2 | (n,elastic) | 5.513 (b) | 6.220 (b) | 1.128 | − | 2.272 (b) | 4.638 (b) | 
| 4 | (n,inelastic) | ( E-thr = 206.2 keV ) | 494.6 (mb) | 1.167 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.888 MeV ) | 1.134 (b) | 1.628 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.37 MeV ) | − | 524.5 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.094 MeV ) | 1.341 (mb) | 1.247 (μb) | |||
| 28 | (n,np) | ( E-thr = 7.544 MeV ) | 122.4 (mb) | 45.91 (μb) | |||
| 102 | (n,γ) | 2.583 (b) | 2.582 (b) | 0.999 | 25.66 (b) | 1.012 (mb) | 31.63 (mb) | 
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 16.23 (mb) | 35.76 (mb) | 1.716 (mb) | 
| 104 | (n,d) | ( E-thr = 5.210 MeV ) | 784.4 (μb) | 173.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.456 MeV ) | 17.21 (μb) | 9.471 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 4.952 MeV ) | 38.66 (nb) | 130.1e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.647 (mb) | 10.65 (mb) | 373.3 (μb) | 
| 111 | (n,2p) | ( E-thr = 5.485 MeV ) | 15.32 (μb) | 3.681 (nb) | |||
| 
      These cross sections are calculated from JENDL-3.2 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 :
      
     
  |