93-Np-234

Reaction 0.0253-eV Maxwellian
Average
g-factor Resonance
Integral
14-MeV Fiss. Spec.
Average
total 2.123 (kb) 2.128 (kb) 1.002 5.874 (b) 7.807 (b)
elastic 11.43 (b) 12.90 (b) 1.129 2.742 (b) 4.262 (b)
inelastic ( E-thr = 30.13 keV ) 411.1 (mb) 1.030 (b)
(n,2n) ( E-thr = 6.091 MeV ) 47.30 (mb) 1.478 (mb)
(n,3n) ( E-thr = 13.61 MeV ) 905.4e-12 (b) 1.472 (nb)
fission 2.001 (kb) 2.001 (kb) 1.000 1.166 (kb) 2.670 (b) 2.477 (b)
(n,fission) 2.001 (kb) 2.001 (kb) 1.000 1.166 (kb) 1.599 (b) 2.467 (b)
(n,n,fiss) ( E-thr = 3.000 MeV ) 823.4 (mb) 10.45 (mb)
(n,2n,fiss) ( E-thr = 6.500 MeV ) 251.7 (mb) 124.9 (μb)
(n,3nfiss) ( E-thr = 14.00 MeV ) 0.000 (b) 183.9e-12 (b)
capture 110.1 (b) 110.2 (b) 1.002 63.05 (b) 955.2 (μb) 35.58 (mb)
 
νp 2.632 4.564
νd 3.350e-3 2.869e-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).

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.