53-I-132
Spin
Level energy(keV) Spin & Parity
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ground state 4+
1.20000E+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)
131.907993514 ± 0.000004364 (amu) [mass excess = -85703.490 ± 4.065 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
3575.473 ± 4.065 (keV)
Strong Gamma-rays from Decay of I-132 (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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22. -- IT
98.0 3.72 IT
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667.71 98.7 B-
772.60 75.6 B-
954.55 17.57 B-
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599.8 14. B-
667.71 ? 13.94 B-
772.60 ? 13.96 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- 1.387 H 15
B- 2.295 H 13
IT 1.387 H 15
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
I -131 (Z= 53, A=131), MT=102 (n,γ)
Xe-132 (Z= 54, A=132), MT=103 (n,p)
Xe-133 (Z= 54, A=133), MT= 28 (n,np)
Xe-133 (Z= 54, A=133), MT=104 (n,d)
Xe-134 (Z= 54, A=134), MT= 32 (n,nd)
Xe-134 (Z= 54, A=134), MT=105 (n,t)
Cs-133 (Z= 55, A=133), MT=111 (n,2p)
Cs-134 (Z= 55, A=134), MT= 44 (n,n2p)
Cs-134 (Z= 55, A=134), MT=106 (n,3He)
Cs-134 (Z= 55, A=134), MT=115 (n,pd)
Cs-135 (Z= 55, A=135), MT= 34 (n,n3He)
Cs-135 (Z= 55, A=135), MT=107 (n,α)
Cs-135 (Z= 55, A=135), MT=116 (n,pt)
Cs-136 (Z= 55, A=136), MT= 22 (n,nα)
Cs-137 (Z= 55, A=137), 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-132 U-235 Thermal 1.039340e-04 6.651750e-05
I-132 U-235 Fast 5.366500e-05 3.434560e-05
I-132 U-235 High 2.975210e-03 1.904140e-03
I-132 U-238 Fast 1.044040e-04 6.681830e-05
I-132 U-238 High 7.076170e-04 4.528750e-04
I-132 Pu-239 Thermal 1.514810e-03 9.694780e-04
I-132 Pu-239 Fast 9.158770e-04 5.861610e-04
I-132 Pu-239 High 7.083700e-03 4.533560e-03
I-132 Pu-241 Thermal 3.478250e-04 2.226070e-04
I-132 Pu-241 Fast 1.611640e-04 1.031450e-04
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I-132m U-235 Thermal 7.840600e-05 5.017990e-05
I-132m U-235 Fast 4.855410e-05 3.107460e-05
I-132m U-235 High 4.833740e-03 3.093600e-03
I-132m U-238 Fast 9.446040e-05 6.045470e-05
I-132m U-238 High 1.149650e-03 7.357730e-04
I-132m Pu-239 Thermal 1.142750e-03 7.313610e-04
I-132m Pu-239 Fast 8.286510e-04 5.303360e-04
I-132m Pu-239 High 1.150870e-02 7.365550e-03
I-132m Pu-241 Thermal 2.623940e-04 1.679320e-04
I-132m Pu-241 Fast 1.458150e-04 9.332170e-05
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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-132 U-235 Thermal 4.305740e-02 2.755680e-02
I-132 U-235 Fast 4.661070e-02 2.983090e-02
I-132 U-235 High 4.809040e-02 3.025270e-02
I-132 U-238 Fast 5.153050e-02 3.293880e-02
I-132 U-238 High 4.827750e-02 3.074280e-02
I-132 Pu-239 Thermal 5.388560e-02 3.448680e-02
I-132 Pu-239 Fast 5.315770e-02 3.402100e-02
I-132 Pu-239 High 4.995460e-02 3.083690e-02
I-132 Pu-241 Thermal 4.561750e-02 2.919520e-02
I-132 Pu-241 Fast 4.704660e-02 3.010990e-02
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I-132m U-235 Thermal 7.840600e-05 5.017990e-05
I-132m U-235 Fast 4.855410e-05 3.107460e-05
I-132m U-235 High 4.833740e-03 3.089020e-03
I-132m U-238 Fast 9.446040e-05 6.043260e-05
I-132m U-238 High 1.149650e-03 7.349760e-04
I-132m Pu-239 Thermal 1.142750e-03 7.313610e-04
I-132m Pu-239 Fast 8.286510e-04 5.303360e-04
I-132m Pu-239 High 1.150870e-02 7.360780e-03
I-132m Pu-241 Thermal 2.623940e-04 1.679050e-04
I-132m Pu-241 Fast 1.458150e-04 9.332170e-05
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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