53-I-129
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)
128.904983669 ± 0.000003401 (amu) [mass excess = -88507.142 ± 3.168 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
188.915 ± 3.168 (keV)
Strong Gamma-rays from Decay of I-129 (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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39.58 7.51 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- 1.57E7 Y 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, I-129.
Figures of cross sections, I-129: 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= 2 (Elastic scattering)
I -129 (Z= 53, A=129), MT= 4 (Inelastic scattering)
I -130 (Z= 53, A=130), MT= 16 (n,2n)
I -131 (Z= 53, A=131), MT= 17 (n,3n)
Xe-129 (Z= 54, A=129), MT=103 (n,p)
Xe-130 (Z= 54, A=130), MT= 28 (n,np)
Xe-130 (Z= 54, A=130), MT=104 (n,d)
Xe-131 (Z= 54, A=131), MT= 32 (n,nd)
Xe-131 (Z= 54, A=131), MT=105 (n,t)
Cs-133 (Z= 55, A=133), MT= 22 (n,nα)
Cs-134 (Z= 55, A=134), 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)
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I-129 U-235 High 3.539850e-05 2.265500e-05
I-129 U-238 High 9.250070e-07 5.920050e-07
I-129 Pu-239 Thermal 3.849390e-12 2.463610e-12
I-129 Pu-239 Fast 2.279630e-12 1.458960e-12
I-129 Pu-239 High 2.492720e-04 1.595330e-04
I-129 Pu-241 Thermal 5.910960e-14 3.783010e-14
I-129 Pu-241 Fast 8.683470e-14 5.557420e-14
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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-129 U-235 Thermal 5.432070e-03 1.414680e-06
I-129 U-235 Fast 8.359600e-03 7.973980e-06
I-129 U-235 High 2.997050e-02 4.641650e-03
I-129 U-238 Fast 1.007730e-02 3.607380e-05
I-129 U-238 High 1.949470e-02 1.786620e-03
I-129 Pu-239 Thermal 1.321300e-02 7.431700e-04
I-129 Pu-239 Fast 1.405450e-02 9.827470e-04
I-129 Pu-239 High 2.940880e-02 5.814280e-03
I-129 Pu-241 Thermal 8.029930e-03 1.893500e-03
I-129 Pu-241 Fast 1.139130e-02 9.748670e-04
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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