54-Xe-135
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
5.26562E+02 11/2-
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)
134.907227780 ± 0.000004455 (amu) [mass excess = -86416.766 ± 4.150 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1165.048 ± 4.071 (keV)
Strong Gamma-rays from Decay of Xe-135 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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249.79 90. B-
407.99 0.36 B-
608.18 2.9 B-
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526.56 80.56 IT
786.9 4.E-03 B-
1133. 3.E-04 B-
1358. 2.E-04 B-
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 9.14 H 2
B- 15.29 M 5
IT 15.29 M 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Xe-135.
Figures of cross sections, Xe-135: 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-134 (Z= 54, A=134), MT=102 (n,γ)
Xe-135 (Z= 54, A=135), MT= 2 (Elastic scattering)
Xe-135 (Z= 54, A=135), MT= 4 (Inelastic scattering)
Xe-136 (Z= 54, A=136), MT= 16 (n,2n)
Cs-135 (Z= 55, A=135), MT=103 (n,p)
Cs-136 (Z= 55, A=136), MT= 28 (n,np)
Cs-136 (Z= 55, A=136), MT=104 (n,d)
Cs-137 (Z= 55, A=137), MT= 32 (n,nd)
Cs-137 (Z= 55, A=137), MT= 41 (n,2np)
Cs-137 (Z= 55, A=137), MT=105 (n,t)
Ba-138 (Z= 56, A=138), MT=107 (n,α)
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-135 U-235 Thermal 7.507970e-04 4.504780e-05
Xe-135 U-235 Fast 8.010140e-04 1.842330e-04
Xe-135 U-235 High 2.599310e-03 4.158890e-04
Xe-135 U-238 Fast 7.067870e-05 4.523430e-05
Xe-135 U-238 High 6.001780e-04 6.601950e-05
Xe-135 Pu-239 Thermal 3.124130e-03 1.249650e-04
Xe-135 Pu-239 Fast 3.840130e-03 2.304080e-04
Xe-135 Pu-239 High 3.985130e-03 1.793310e-03
Xe-135 Pu-241 Thermal 6.649330e-04 5.319470e-05
Xe-135 Pu-241 Fast 6.610580e-04 4.230780e-04
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Xe-135m U-235 Thermal 1.811650e-03 1.086990e-04
Xe-135m U-235 Fast 2.244670e-03 1.436590e-03
Xe-135m U-235 High 1.192200e-02 3.815030e-03
Xe-135m U-238 Fast 1.980620e-04 1.267600e-04
Xe-135m U-238 High 2.752770e-03 1.761770e-03
Xe-135m Pu-239 Thermal 7.538430e-03 4.824590e-03
Xe-135m Pu-239 Fast 1.076110e-02 6.887120e-03
Xe-135m Pu-239 High 1.827810e-02 8.225140e-03
Xe-135m Pu-241 Thermal 1.604460e-03 1.026850e-03
Xe-135m Pu-241 Fast 1.852470e-03 1.185580e-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-135 U-235 Thermal 6.523010e-02 4.733700e-04
Xe-135 U-235 Fast 6.578910e-02 6.782690e-04
Xe-135 U-235 High 5.674920e-02 3.851060e-03
Xe-135 U-238 Fast 6.922760e-02 8.067420e-04
Xe-135 U-238 High 5.832340e-02 1.328860e-03
Xe-135 Pu-239 Thermal 7.604770e-02 7.608870e-04
Xe-135 Pu-239 Fast 7.538660e-02 2.380780e-03
Xe-135 Pu-239 High 6.184480e-02 1.888020e-02
Xe-135 Pu-241 Thermal 7.162300e-02 1.436860e-03
Xe-135 Pu-241 Fast 7.054040e-02 1.422420e-03
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Xe-135m U-235 Thermal 1.219580e-02 1.157360e-03
Xe-135m U-235 Fast 1.264130e-02 2.879950e-03
Xe-135m U-235 High 1.891920e-02 3.009020e-03
Xe-135m U-238 Fast 1.162460e-02 1.257910e-03
Xe-135m U-238 High 1.186150e-02 2.694140e-03
Xe-135m Pu-239 Thermal 1.837290e-02 5.623160e-03
Xe-135m Pu-239 Fast 2.083340e-02 6.405440e-03
Xe-135m Pu-239 High 2.483700e-02 7.743220e-03
Xe-135m Pu-241 Thermal 1.309640e-02 2.285690e-03
Xe-135m Pu-241 Fast 1.312460e-02 3.003470e-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