53-I-130
Spin
Level energy(keV) Spin & Parity
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ground state 5+
3.99525E+01 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)
129.906670193 ± 0.000003401 (amu) [mass excess = -86936.155 ± 3.168 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2944.307 ± 3.168 (keV)
Strong Gamma-rays from Decay of I-130 (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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536.07 99. B-
668.54 96.03 B-
739.51 82.17 B-
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39.96 0.02 IT
536.07 15.68 B-
586.05 1.07 B-
1614.10 0.45 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- 12.36 H 1
B- 8.84 M 6
IT 8.84 M 6
Cross Sections (taken from JENDL-4.0)
Table of cross sections, I-130.
Figures of cross sections, I-130: 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 -129 (Z= 53, A=129), MT=102 (n,γ)
I -130 (Z= 53, A=130), MT= 2 (Elastic scattering)
I -130 (Z= 53, A=130), MT= 4 (Inelastic scattering)
I -131 (Z= 53, A=131), MT= 16 (n,2n)
Xe-130 (Z= 54, A=130), MT=103 (n,p)
Xe-131 (Z= 54, A=131), MT= 28 (n,np)
Xe-131 (Z= 54, A=131), MT=104 (n,d)
Xe-132 (Z= 54, A=132), MT= 32 (n,nd)
Xe-132 (Z= 54, A=132), MT=105 (n,t)
Cs-133 (Z= 55, A=133), MT= 34 (n,n3He)
Cs-133 (Z= 55, A=133), MT=107 (n,α)
Cs-133 (Z= 55, A=133), MT=116 (n,pt)
Cs-134 (Z= 55, A=134), MT= 22 (n,nα)
Cs-135 (Z= 55, A=135), MT= 24 (n,2nα)
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)
-----------------------------------------------------------
I-130 U-235 Thermal 1.550950e-06 9.926060e-07
I-130 U-235 Fast 1.300280e-07 8.321760e-08
I-130 U-235 High 2.129290e-04 1.362750e-04
I-130 U-238 Fast 3.097520e-14 1.982410e-14
I-130 U-238 High 7.829980e-06 5.011180e-06
I-130 Pu-239 Thermal 3.287870e-05 2.104230e-05
I-130 Pu-239 Fast 2.206620e-05 1.412240e-05
I-130 Pu-239 High 1.087970e-03 6.963010e-04
I-130 Pu-241 Thermal 5.896370e-12 3.773670e-12
I-130 Pu-241 Fast 3.386610e-12 2.167430e-12
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I-130m U-235 Thermal 6.615300e-07 4.233800e-07
I-130m U-235 Fast 4.760580e-08 3.046760e-08
I-130m U-235 High 4.705750e-05 3.011680e-05
I-130m U-238 Fast 1.134060e-14 7.257990e-15
I-130m U-238 High 1.730430e-06 1.107470e-06
I-130m Pu-239 Thermal 1.402390e-05 8.975300e-06
I-130m Pu-239 Fast 8.078890e-06 5.170490e-06
I-130m Pu-239 High 2.404420e-04 1.538830e-04
I-130m Pu-241 Thermal 2.515000e-12 1.609600e-12
I-130m Pu-241 Fast 1.239910e-12 7.935410e-13
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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-130 U-235 Thermal 2.106630e-06 1.348240e-06
I-130 U-235 Fast 1.700170e-07 1.088100e-07
I-130 U-235 High 2.524570e-04 1.614970e-04
I-130 U-238 Fast 4.050130e-14 2.592080e-14
I-130 U-238 High 9.283540e-06 5.940160e-06
I-130 Pu-239 Thermal 4.465880e-05 2.858160e-05
I-130 Pu-239 Fast 2.885250e-05 1.846560e-05
I-130 Pu-239 High 1.289940e-03 8.255620e-04
I-130 Pu-241 Thermal 8.008960e-12 5.125740e-12
I-130 Pu-241 Fast 4.428140e-12 2.834010e-12
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I-130m U-235 Thermal 6.615300e-07 4.233800e-07
I-130m U-235 Fast 4.760580e-08 3.046760e-08
I-130m U-235 High 4.705750e-05 3.007220e-05
I-130m U-238 Fast 1.134060e-14 7.255340e-15
I-130m U-238 High 1.730430e-06 1.106270e-06
I-130m Pu-239 Thermal 1.402390e-05 8.975300e-06
I-130m Pu-239 Fast 8.078890e-06 5.170490e-06
I-130m Pu-239 High 2.404420e-04 1.537830e-04
I-130m Pu-241 Thermal 2.515000e-12 1.609340e-12
I-130m Pu-241 Fast 1.239910e-12 7.935410e-13
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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