92-U-236

MT Reaction 0.0253-eV Maxwellian
Average
g-factor Resonance
Integral
14-MeV Fiss. Spec.
Average
1 (n,total) 15.95 (b) 17.36 (b) 1.088 5.889 (b) 7.816 (b)
2 (n,elastic) 10.83 (b) 12.22 (b) 1.128 2.712 (b) 4.829 (b)
4 (n,inelastic) ( E-thr = 45.44 keV ) 499.0 (mb) 2.291 (b)
16 (n,2n) ( E-thr = 6.573 MeV ) 940.4 (mb) 7.503 (mb)
17 (n,3n) ( E-thr = 11.89 MeV ) 121.9 (mb) 18.38 (μb)
18 (n,fission) 259.4 (μb) 260.7 (μb) 1.005 2.225 (b) 1.611 (b) 579.2 (mb)
19 (n,f) 259.4 (μb) 260.7 (μb) 1.005 1.870 (b) 753.7 (mb) 562.1 (mb)
20 (n,nf) ( E-thr = 2.500 MeV ) 710.9 (mb) 17.09 (mb)
21 (n,2nf) ( E-thr = 10.00 MeV ) 146.4 (mb) 19.53 (μb)
37 (n,4n) ( E-thr = 18.77 MeV ) 13.79e-12 (b)
38 (n,3nf) ( E-thr = 14.50 MeV ) 17.74 (nb)
102 (n,γ) 5.123 (b) 5.138 (b) 1.003 353.4 (b) 848.9 (μb) 107.5 (mb)
 
456 νp 2.361 4.417
455 νd 2.250e-2 1.398e-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 :
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.