53-I-134
Spin
Level energy(keV) Spin & Parity
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ground state (4)+
3.16490E+02 (8)-
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)
133.909758836 ± 0.000005916 (amu) [mass excess = -84059.102 ± 5.511 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
4065.201 ± 5.515 (keV)
Strong Gamma-rays from Decay of I-134 (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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234.3 1.59 B-
847. 2.3 B-
885. 2.3 B-
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847.02 95.7 B-
884.09 65.08 B-
1072.55 14.93 B-
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44.4 10.84 IT
272.1 79.14 IT
316.3 < 0.47 IT
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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- 3.52 M 4
B- 52.5 M 2
IT 3.52 M 4
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
I -135 (Z= 53, A=135), MT= 16 (n,2n)
Xe-134 (Z= 54, A=134), MT=103 (n,p)
Xe-135 (Z= 54, A=135), MT= 28 (n,np)
Xe-135 (Z= 54, A=135), MT=104 (n,d)
Xe-136 (Z= 54, A=136), MT= 32 (n,nd)
Xe-136 (Z= 54, A=136), MT=105 (n,t)
Cs-135 (Z= 55, A=135), MT=111 (n,2p)
Cs-136 (Z= 55, A=136), MT= 44 (n,n2p)
Cs-136 (Z= 55, A=136), MT=106 (n,3He)
Cs-136 (Z= 55, A=136), MT=115 (n,pd)
Cs-137 (Z= 55, A=137), MT= 34 (n,n3He)
Cs-137 (Z= 55, A=137), MT=107 (n,α)
Cs-137 (Z= 55, A=137), MT=116 (n,pt)
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-134 U-235 Thermal 4.971490e-03 2.982890e-04
I-134 U-235 Fast 5.726960e-03 1.832630e-03
I-134 U-235 High 1.092580e-02 3.496270e-03
I-134 U-238 Fast 4.014420e-03 4.415860e-04
I-134 U-238 High 5.918430e-03 9.469480e-04
I-134 Pu-239 Thermal 1.508950e-02 9.053700e-04
I-134 Pu-239 Fast 1.244480e-02 3.982320e-03
I-134 Pu-239 High 1.256440e-02 4.020620e-03
I-134 Pu-241 Thermal 7.761950e-03 4.967650e-03
I-134 Pu-241 Fast 6.128100e-03 3.921980e-03
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I-134m U-235 Thermal 3.659570e-03 2.342130e-03
I-134m U-235 Fast 5.078630e-03 3.250320e-03
I-134m U-235 High 1.737940e-02 3.997270e-03
I-134m U-238 Fast 3.559960e-03 2.278380e-03
I-134m U-238 High 9.414290e-03 6.025150e-03
I-134m Pu-239 Thermal 1.110760e-02 3.554410e-03
I-134m Pu-239 Fast 1.103590e-02 3.531510e-03
I-134m Pu-239 High 1.998590e-02 4.596760e-03
I-134m Pu-241 Thermal 5.713660e-03 2.571150e-03
I-134m Pu-241 Fast 5.434350e-03 3.477990e-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-134 U-235 Thermal 7.820540e-02 4.696870e-03
I-134 U-235 Fast 7.627720e-02 1.742260e-03
I-134 U-235 High 5.196760e-02 4.153610e-03
I-134 U-238 Fast 7.633280e-02 4.592250e-03
I-134 U-238 High 6.384930e-02 7.005570e-03
I-134 Pu-239 Thermal 7.406460e-02 4.550610e-03
I-134 Pu-239 Fast 7.113860e-02 2.071200e-03
I-134 Pu-239 High 4.910630e-02 5.391220e-03
I-134 Pu-241 Thermal 7.879150e-02 2.205760e-03
I-134 Pu-241 Fast 7.496470e-02 2.099410e-03
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I-134m U-235 Thermal 3.659570e-03 2.342120e-03
I-134m U-235 Fast 5.078630e-03 3.250320e-03
I-134m U-235 High 1.737940e-02 3.991420e-03
I-134m U-238 Fast 3.559960e-03 2.277540e-03
I-134m U-238 High 9.414290e-03 6.018620e-03
I-134m Pu-239 Thermal 1.110760e-02 3.554930e-03
I-134m Pu-239 Fast 1.103590e-02 3.532020e-03
I-134m Pu-239 High 1.998590e-02 4.593790e-03
I-134m Pu-241 Thermal 5.713660e-03 2.570730e-03
I-134m Pu-241 Fast 5.434350e-03 3.477990e-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