54-Xe-136
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)
135.907214484 ± 0.000000011 (amu) [mass excess = -86429.152 ± 0.010 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-90.238 ± 1.877 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Xe-136.
Figures of cross sections, Xe-136: 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
Xe-135 (Z= 54, A=135), MT=102 (n,γ)
Xe-136 (Z= 54, A=136), MT= 2 (Elastic scattering)
Xe-136 (Z= 54, A=136), MT= 4 (Inelastic scattering)
Cs-136 (Z= 55, A=136), MT=103 (n,p)
Cs-137 (Z= 55, A=137), MT= 28 (n,np)
Cs-137 (Z= 55, A=137), MT=104 (n,d)
Ba-140 (Z= 56, A=140), MT= 22 (n,nα)
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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Xe-136 U-235 Thermal 2.189090e-02 9.850910e-03
Xe-136 U-235 Fast 1.708720e-02 1.879590e-03
Xe-136 U-235 High 2.174490e-02 6.958370e-03
Xe-136 U-238 Fast 2.444100e-03 1.564220e-03
Xe-136 U-238 High 8.054560e-03 5.154920e-03
Xe-136 Pu-239 Thermal 3.478650e-02 1.113170e-02
Xe-136 Pu-239 Fast 2.924130e-02 1.315860e-02
Xe-136 Pu-239 High 3.121210e-02 9.987870e-03
Xe-136 Pu-241 Thermal 1.083990e-02 3.468750e-03
Xe-136 Pu-241 Fast 1.080930e-02 3.458980e-03
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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)
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Xe-136 U-235 Thermal 6.309660e-02 2.230600e-04
Xe-136 U-235 Fast 6.207190e-02 3.212780e-04
Xe-136 U-235 High 5.083260e-02 2.031750e-03
Xe-136 U-238 Fast 7.004610e-02 1.419220e-03
Xe-136 U-238 High 5.638990e-02 1.134340e-03
Xe-136 Pu-239 Thermal 7.048440e-02 7.050450e-04
Xe-136 Pu-239 Fast 6.942200e-02 6.943320e-04
Xe-136 Pu-239 High 5.472770e-02 2.187730e-03
Xe-136 Pu-241 Thermal 7.099870e-02 9.966970e-04
Xe-136 Pu-241 Fast 6.675090e-02 1.334750e-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