92-U-233

MT Reaction 0.0253-eV Maxwellian
Average
g-factor Resonance
Integral
14-MeV Fiss. Spec.
Average
1 (n,total) 588.8 (b) 590.1 (b) 1.002 5.798 (b) 7.651 (b)
2 (n,elastic) 12.18 (b) 13.72 (b) 1.126 2.883 (b) 4.474 (b)
4 (n,inelastic) ( E-thr = 40.52 keV ) 368.3 (mb) 1.208 (b)
16 (n,2n) ( E-thr = 5.787 MeV ) 181.2 (mb) 1.843 (mb)
17 (n,3n) ( E-thr = 13.09 MeV ) 271.1 (μb) 673.3 (nb)
18 (n,fission) 531.3 (b) 529.7 (b) 0.997 775.4 (b) 2.364 (b) 1.908 (b)
19 (n,f) 531.3 (b) 529.7 (b) 0.997 774.9 (b) 1.100 (b) 1.883 (b)
20 (n,nf) ( E-thr = 1.800 MeV ) 892.5 (mb) 24.48 (mb)
21 (n,2nf) ( E-thr = 7.000 MeV ) 371.1 (mb) 69.56 (μb)
37 (n,4n) ( E-thr = 18.99 MeV ) 857.6e-15 (b)
38 (n,3nf) ( E-thr = 15.50 MeV ) 136.5e-12 (b)
102 (n,γ) 45.26 (b) 46.74 (b) 1.033 139.4 (b) 583.0 (μb) 58.96 (mb)
 
456 νp 2.478 4.380
455 νd 6.700e-3 4.100e-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.