56-Ba-138
Spin
Level energy(keV) Spin & Parity
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ground state 0+
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
137.905246995 ± 0.000000306 (amu) [mass excess = -88261.856 ± 0.285 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1739.960 ± 3.431 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ba-138.
Figures of cross sections, Ba-138: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Ba-137 (Z= 56, A=137), MT=102 (n,γ)
Ba-138 (Z= 56, A=138), MT= 2 (Elastic scattering)
Ba-138 (Z= 56, A=138), MT= 4 (Inelastic scattering)
Ba-140 (Z= 56, A=140), MT= 17 (n,3n)
La-138 (Z= 57, A=138), MT=103 (n,p)
La-139 (Z= 57, A=139), MT= 28 (n,np)
La-139 (Z= 57, A=139), MT=104 (n,d)
La-140 (Z= 57, A=140), MT= 32 (n,nd)
La-140 (Z= 57, A=140), MT=105 (n,t)
Ce-140 (Z= 58, A=140), MT=106 (n,3He)
Ce-141 (Z= 58, A=141), MT=107 (n,α)
Ce-142 (Z= 58, A=142), MT= 22 (n,nα)
Nd-145 (Z= 60, A=145), MT=108 (n,2α)
Nd-146 (Z= 60, A=146), MT= 29 (n,n2α)
Nd-147 (Z= 60, A=147), MT= 30 (n,2n2α)
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Ba-138 U-235 Thermal 4.109460e-05 2.630050e-05
Ba-138 U-235 Fast 2.125610e-05 1.360390e-05
Ba-138 U-235 High 9.925710e-04 6.352460e-04
Ba-138 U-238 Fast 2.040760e-06 1.306090e-06
Ba-138 U-238 High 4.187560e-05 2.680040e-05
Ba-138 Pu-239 Thermal 5.257780e-04 3.364970e-04
Ba-138 Pu-239 Fast 4.889400e-04 3.129220e-04
Ba-138 Pu-239 High 2.947360e-03 1.886310e-03
Ba-138 Pu-241 Thermal 3.306540e-05 2.116180e-05
Ba-138 Pu-241 Fast 3.451400e-05 2.208900e-05
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
-----------------------------------------------------------
Ba-138 U-235 Thermal 6.756100e-02 3.573240e-04
Ba-138 U-235 Fast 6.665300e-02 4.916120e-04
Ba-138 U-235 High 4.599450e-02 2.756620e-03
Ba-138 U-238 Fast 5.758560e-02 8.077030e-04
Ba-138 U-238 High 4.885830e-02 1.367590e-03
Ba-138 Pu-239 Thermal 6.122280e-02 6.128260e-04
Ba-138 Pu-239 Fast 6.124510e-02 4.293170e-04
Ba-138 Pu-239 High 4.131920e-02 4.542550e-03
Ba-138 Pu-241 Thermal 6.603790e-02 6.606520e-04
Ba-138 Pu-241 Fast 6.140770e-02 3.688930e-03
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data