53-I-135
Spin
Level energy(keV) Spin & Parity
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ground state 7/2+
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)
134.910048847 ± 0.000005798 (amu) [mass excess = -83788.959 ± 5.402 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2627.807 ± 4.990 (keV)
Strong Gamma-rays from Decay of I-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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1131.51 22.59 B-
1260.41 28.7 B-
1678.03 9.56 B-
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1131.51 22.59 B-
1260.41 28.7 B-
1678.03 9.56 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- 6.57 H 2
B- 6.58 H 3
Cross Sections (taken from JENDL-4.0)
Table of cross sections, I-135.
Figures of cross sections, I-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
I -135 (Z= 53, A=135), MT= 2 (Elastic scattering)
I -135 (Z= 53, A=135), MT= 4 (Inelastic scattering)
Xe-135 (Z= 54, A=135), MT=103 (n,p)
Xe-136 (Z= 54, A=136), MT= 28 (n,np)
Xe-136 (Z= 54, A=136), MT=104 (n,d)
Cs-136 (Z= 55, A=136), MT=111 (n,2p)
Cs-137 (Z= 55, A=137), MT= 44 (n,n2p)
Cs-137 (Z= 55, A=137), MT=106 (n,3He)
Cs-137 (Z= 55, A=137), MT=115 (n,pd)
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-135 U-235 Thermal 2.922920e-02 8.184180e-04
I-135 U-235 Fast 3.595840e-02 2.876670e-03
I-135 U-235 High 3.138840e-02 5.022140e-03
I-135 U-238 Fast 1.355070e-02 4.336230e-03
I-135 U-238 High 2.571660e-02 5.914820e-03
I-135 Pu-239 Thermal 4.286800e-02 2.572080e-03
I-135 Pu-239 Fast 3.921340e-02 4.313480e-03
I-135 Pu-239 High 3.231430e-02 1.034060e-02
I-135 Pu-241 Thermal 3.009190e-02 6.921120e-03
I-135 Pu-241 Fast 2.847460e-02 9.111850e-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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I-135 U-235 Thermal 6.266820e-02 8.922490e-04
I-135 U-235 Fast 6.274390e-02 2.527510e-03
I-135 U-235 High 4.222870e-02 3.374960e-03
I-135 U-238 Fast 6.895930e-02 1.069960e-03
I-135 U-238 High 5.497090e-02 1.103260e-03
I-135 Pu-239 Thermal 6.538580e-02 1.832030e-03
I-135 Pu-239 Fast 6.078620e-02 2.432810e-03
I-135 Pu-239 High 3.958250e-02 1.780450e-02
I-135 Pu-241 Thermal 6.935410e-02 1.945610e-03
I-135 Pu-241 Fast 6.802740e-02 7.500520e-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