96-Cm-246

MT Reaction 0.0253-eV Maxwellian
Average
g-factor Resonance
Integral
14-MeV Fiss. Spec.
Average
1 (n,total) 10.45 (b) 11.64 (b) 1.114 5.926 (b) 8.023 (b)
2 (n,elastic) 9.222 (b) 10.41 (b) 1.129 2.066 (b) 4.721 (b)
4 (n,inelastic) ( E-thr = 43.03 keV ) 397.7 (mb) 1.973 (b)
16 (n,2n) ( E-thr = 6.484 MeV ) 670.5 (mb) 5.644 (mb)
17 (n,3n) ( E-thr = 12.03 MeV ) 56.66 (mb) 7.677 (μb)
18 (n,fission) 44.01 (mb) 44.14 (mb) 1.003 7.599 (b) 2.732 (b) 1.250 (b)
19 (n,f) 44.01 (mb) 44.14 (mb) 1.003 7.106 (b) 1.196 (b) 1.227 (b)
20 (n,nf) ( E-thr = 1.403 MeV ) 1.399 (b) 23.13 (mb)
21 (n,2nf) ( E-thr = 9.000 MeV ) 135.2 (mb) 19.97 (μb)
38 (n,3nf) ( E-thr = 13.50 MeV ) 9.414 (μb) 41.51 (nb)
102 (n,γ) 1.179 (b) 1.186 (b) 1.006 113.1 (b) 1.122 (mb) 70.45 (mb)
 
456 νp 2.980 5.181
455 νd 9.160e-3 6.400e-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.