92-U-235

MT Reaction 0.0253-eV Maxwellian
Average
g-factor Resonance
Integral
14-MeV Fiss. Spec.
Average
1 (n,total) 698.9 (b) 686.2 (b) 0.982 5.894 (b) 7.628 (b)
2 (n,elastic) 15.12 (b) 16.95 (b) 1.121 2.839 (b) 4.451 (b)
4 (n,inelastic) ( E-thr = 77.33 eV ) 420.3 (mb) 1.858 (b)
16 (n,2n) ( E-thr = 5.320 MeV ) 548.2 (mb) 12.43 (mb)
17 (n,3n) ( E-thr = 12.19 MeV ) 30.33 (mb) 6.947 (μb)
18 (n,fission) 585.1 (b) 571.4 (b) 0.977 274.4 (b) 2.053 (b) 1.218 (b)
19 (n,f) 585.1 (b) 571.4 (b) 0.977 274.0 (b) 780.9 (mb) 1.201 (b)
20 (n,nf) ( E-thr = 3.500 MeV ) 766.4 (mb) 16.78 (mb)
21 (n,2nf) ( E-thr = 7.500 MeV ) 506.1 (mb) 92.33 (μb)
37 (n,4n) ( E-thr = 17.98 MeV ) 161.4e-12 (b)
38 (n,3nf) ( E-thr = 14.50 MeV ) 5.251 (nb)
102 (n,γ) 98.71 (b) 97.83 (b) 0.991 139.0 (b) 889.7 (μb) 87.41 (mb)
 
456 νp 2.420 4.497
455 νd 1.585e-2 9.425e-3

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 :
σmacs(T) =
2
 
 
π
EU
 
EL
σ(E,T) ⋅ E ⋅ exp (
E
  
kBT
) dE
 
EU
 
EL
E ⋅ exp (
E
  
kBT
) dE
,
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 :
σri(T) =
EU
 
EL
σ(E,T) ⋅
1
 
E
dE ,
with  EL = 0.5 eV  and  EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
σfacs(T) =
EU
 
EL
σ(E,T) ⋅
 
4
 
πa3b
⋅ exp (
ab E
     
4 a
) ⋅ sinh
 
bE
dE
 
EU
 
EL
 
4
 
πa3b
⋅ exp (
ab E
     
4 a
) ⋅ sinh
 
bE
dE
,
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 :
g(T) =
σmacs(T)
 
σ(0.0253 eV,T)
 .


νp, νd : numbers of prompt and delayed neutrons per fission.