53-I-127
Spin
Level energy(keV) Spin & Parity
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ground state 5/2+
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)
126.904471853 ± 0.000003915 (amu) [mass excess = -88983.895 ± 3.647 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-662.349 ± 2.044 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, I-127.
Figures of cross sections, I-127: 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 -127 (Z= 53, A=127), MT= 2 (Elastic scattering)
I -127 (Z= 53, A=127), MT= 4 (Inelastic scattering)
I -129 (Z= 53, A=129), MT= 17 (n,3n)
Xe-128 (Z= 54, A=128), MT= 28 (n,np)
Xe-128 (Z= 54, A=128), MT=104 (n,d)
Xe-129 (Z= 54, A=129), MT= 32 (n,nd)
Xe-129 (Z= 54, A=129), MT=105 (n,t)
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-127 U-235 High 8.091090e-07 5.178290e-07
I-127 U-238 High 1.611760e-10 5.157610e-11
I-127 Pu-239 High 6.624300e-06 4.239550e-06
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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-127 U-235 Thermal 1.569650e-03 7.136260e-08
I-127 U-235 Fast 3.057760e-03 4.760220e-06
I-127 U-235 High 2.183720e-02 6.118490e-04
I-127 U-238 Fast 1.364670e-03 2.195360e-06
I-127 U-238 High 1.497180e-02 8.968450e-04
I-127 Pu-239 Thermal 5.062930e-03 4.270110e-07
I-127 Pu-239 Fast 5.008620e-03 2.104790e-07
I-127 Pu-239 High 2.206380e-02 1.322670e-03
I-127 Pu-241 Thermal 2.325130e-03 1.436330e-06
I-127 Pu-241 Fast 3.319830e-03 1.193020e-06
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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