49-In-117
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
3.15302E+02 1/2-
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)
116.904515678 ± 0.000005239 (amu) [mass excess = -88943.073 ± 4.881 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1454.710 ± 4.857 (keV)
Strong Gamma-rays from Decay of In-117 (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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158.6 87. B-
396.6 0.17 B-
552.9 100. B-
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158.6 15.87 B-
861.6 0.02 B-
1020.3 7.E-03 B-
315.30 19.12 IT
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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- 43.2 M 3
B- 116.2 M 3
IT 116.2 M 3
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Sn-117 (Z= 50, A=117), MT=103 (n,p)
Sn-118 (Z= 50, A=118), MT= 28 (n,np)
Sn-118 (Z= 50, A=118), MT=104 (n,d)
Sn-119 (Z= 50, A=119), MT= 32 (n,nd)
Sn-119 (Z= 50, A=119), MT=105 (n,t)
Sb-121 (Z= 51, A=121), MT= 22 (n,nα)
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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In-117 U-235 Thermal 3.663590e-09 2.344700e-09
In-117 U-235 Fast 5.679150e-09 3.634660e-09
In-117 U-235 High 2.058540e-06 1.317470e-06
In-117 U-238 Fast 9.313550e-11 5.960670e-11
In-117 U-238 High 3.456300e-08 2.212040e-08
In-117 Pu-239 Thermal 7.038930e-08 4.504910e-08
In-117 Pu-239 Fast 1.292720e-07 8.273390e-08
In-117 Pu-239 High 3.766670e-05 2.410670e-05
In-117 Pu-241 Thermal 4.151620e-10 2.657030e-10
In-117 Pu-241 Fast 4.136920e-09 2.647630e-09
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In-117m U-235 Thermal 8.482210e-10 5.428620e-10
In-117m U-235 Fast 1.146750e-09 7.339220e-10
In-117m U-235 High 2.596360e-07 1.661680e-07
In-117m U-238 Fast 1.880620e-11 1.203600e-11
In-117m U-238 High 4.359300e-09 2.789950e-09
In-117m Pu-239 Thermal 1.629700e-08 1.043010e-08
In-117m Pu-239 Fast 2.610300e-08 1.670590e-08
In-117m Pu-239 High 4.750760e-06 3.040490e-06
In-117m Pu-241 Thermal 9.612120e-11 6.151760e-11
In-117m Pu-241 Fast 8.353400e-10 5.346180e-10
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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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In-117 U-235 Thermal 7.717760e-05 8.137990e-06
In-117 U-235 Fast 2.200660e-04 7.644980e-05
In-117 U-235 High 6.413550e-03 1.622570e-03
In-117 U-238 Fast 2.236540e-04 7.795940e-05
In-117 U-238 High 3.591120e-03 3.338620e-04
In-117 Pu-239 Thermal 2.692240e-04 6.805390e-05
In-117 Pu-239 Fast 4.244330e-04 1.468460e-04
In-117 Pu-239 High 7.275800e-03 2.498890e-03
In-117 Pu-241 Thermal 1.405820e-04 4.878920e-05
In-117 Pu-241 Fast 5.242350e-04 1.820660e-04
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In-117m U-235 Thermal 9.476830e-05 1.011260e-05
In-117m U-235 Fast 2.777120e-04 1.163040e-04
In-117m U-235 High 7.985770e-03 2.433980e-03
In-117m U-238 Fast 2.850520e-04 8.691890e-05
In-117m U-238 High 4.574660e-03 5.193010e-04
In-117m Pu-239 Thermal 3.307150e-04 1.008060e-04
In-117m Pu-239 Fast 5.173070e-04 2.160800e-04
In-117m Pu-239 High 8.008740e-03 2.441750e-03
In-117m Pu-241 Thermal 1.792480e-04 7.517960e-05
In-117m Pu-241 Fast 6.672350e-04 2.797380e-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