53-I-136
Spin
Level energy(keV) Spin & Parity
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ground state (1-)
6.40000E+02 (6-)
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)
135.914604412 ± 0.000015238 (amu) [mass excess = -79545.478 ± 14.195 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
6883.674 ± 14.195 (keV)
Strong Gamma-rays from Decay of I-136 (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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197.32 78.3 B-
381.36 99.8 B-
1313.02 100. B-
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1313.02 66.7 B-
1321.08 24.81 B-
2289.6 10.41 B-
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240.5 * 3.4 B-
1686.1 * 4.6 B-
1689.0 * 3.9 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- 46.9 S 10
B- 46.9 S 10
B- 83.4 S 10
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
I -135 (Z= 53, A=135), MT=102 (n,γ)
Xe-136 (Z= 54, A=136), MT=103 (n,p)
Cs-137 (Z= 55, A=137), MT=111 (n,2p)
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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I-136 U-235 Thermal 7.674450e-03 6.139570e-04
I-136 U-235 Fast 8.830380e-03 2.825720e-03
I-136 U-235 High 4.440380e-03 1.420920e-03
I-136 U-238 Fast 7.168060e-03 2.293780e-03
I-136 U-238 High 5.736280e-03 1.835610e-03
I-136 Pu-239 Thermal 8.644810e-03 2.766330e-03
I-136 Pu-239 Fast 8.582800e-03 2.746500e-03
I-136 Pu-239 High 3.793000e-03 1.213760e-03
I-136 Pu-241 Thermal 1.204670e-02 3.854970e-03
I-136 Pu-241 Fast 9.106810e-03 2.914190e-03
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I-136m U-235 Thermal 1.799260e-02 1.079560e-03
I-136m U-235 Fast 2.411880e-02 5.547310e-03
I-136m U-235 High 2.009210e-02 6.429500e-03
I-136m U-238 Fast 1.957840e-02 6.265090e-03
I-136m U-238 High 2.595590e-02 8.305880e-03
I-136m Pu-239 Thermal 2.026760e-02 1.621410e-03
I-136m Pu-239 Fast 2.344260e-02 7.501640e-03
I-136m Pu-239 High 1.716280e-02 5.492100e-03
I-136m Pu-241 Thermal 2.824340e-02 9.037870e-03
I-136m Pu-241 Fast 2.487380e-02 7.959620e-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)
-----------------------------------------------------------
I-136 U-235 Thermal 2.091740e-02 1.255370e-03
I-136 U-235 Fast 1.900430e-02 3.045040e-03
I-136 U-235 High 8.001630e-03 1.836580e-03
I-136 U-238 Fast 4.395260e-02 4.818330e-03
I-136 U-238 High 2.001960e-02 3.193230e-03
I-136 Pu-239 Thermal 1.367290e-02 3.144330e-03
I-136 Pu-239 Fast 1.528560e-02 3.514990e-03
I-136 Pu-239 High 5.852760e-03 1.344720e-03
I-136 Pu-241 Thermal 2.892030e-02 6.645020e-03
I-136 Pu-241 Fast 2.815270e-02 4.503520e-03
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I-136m U-235 Thermal 1.811440e-02 1.088860e-03
I-136m U-235 Fast 2.416230e-02 3.874200e-03
I-136m U-235 High 2.011370e-02 4.619360e-03
I-136m U-238 Fast 2.001020e-02 4.600340e-03
I-136m U-238 High 2.609770e-02 5.995920e-03
I-136m Pu-239 Thermal 2.030260e-02 1.218330e-03
I-136m Pu-239 Fast 2.347380e-02 5.399730e-03
I-136m Pu-239 High 1.717050e-02 3.946660e-03
I-136m Pu-241 Thermal 2.838230e-02 6.526760e-03
I-136m Pu-241 Fast 2.502180e-02 5.759260e-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