49-In-116
Spin
Level energy(keV) Spin & Parity
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ground state 1+
1.27268E+02 5+
2.89660E+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)
115.905259995 ± 0.000000236 (amu) [mass excess = -88249.746 ± 0.220 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
3276.249 ± 0.240 (keV)
Strong Gamma-rays from Decay of In-116 (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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463.3 0.25 B-
1252.6 0.03 B-
1293.4 1.3 B-
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416.90 27.22 B-
1097.28 58.51 B-
1293.56 84.8 B-
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162.39 37.2 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- 14.10 S 3
B- 54.29 M 17
IT 2.18 S 4
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
In-115 (Z= 49, A=115), MT=102 (n,γ)
Sn-116 (Z= 50, A=116), MT=103 (n,p)
Sn-117 (Z= 50, A=117), MT= 28 (n,np)
Sn-117 (Z= 50, A=117), MT=104 (n,d)
Sn-118 (Z= 50, A=118), 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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In-116 U-235 Thermal 1.414550e-11 9.053100e-12
In-116 U-235 Fast 1.881800e-11 1.204350e-11
In-116 U-235 High 2.439340e-08 1.561180e-08
In-116 U-238 Fast 2.317470e-13 1.483180e-13
In-116 U-238 High 2.228430e-10 1.426190e-10
In-116 Pu-239 Thermal 4.084160e-10 2.613860e-10
In-116 Pu-239 Fast 5.150760e-10 3.296490e-10
In-116 Pu-239 High 8.174290e-07 5.231540e-07
In-116 Pu-241 Thermal 6.919500e-13 4.428490e-13
In-116 Pu-241 Fast 1.282080e-11 8.205290e-12
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In-116m U-235 Thermal 4.266710e-11 2.730690e-11
In-116m U-235 Thermal 2.006510e-11 1.284160e-11
In-116m U-235 Fast 6.574670e-11 4.207790e-11
In-116m U-235 Fast 3.159560e-11 2.022120e-11
In-116m U-235 High 1.379970e-07 8.831810e-08
In-116m U-235 High 6.969560e-08 4.460510e-08
In-116m U-238 Fast 8.096820e-13 5.181970e-13
In-116m U-238 Fast 3.891050e-13 2.490280e-13
In-116m U-238 High 1.260650e-09 8.068180e-10
In-116m U-238 High 6.366940e-10 4.074840e-10
In-116m Pu-239 Thermal 1.231910e-09 7.884200e-10
In-116m Pu-239 Thermal 5.793290e-10 3.707700e-10
In-116m Pu-239 Fast 1.799590e-09 1.151740e-09
In-116m Pu-239 Fast 8.648190e-10 5.534850e-10
In-116m Pu-239 High 4.624310e-06 2.959560e-06
In-116m Pu-239 High 2.335510e-06 1.494730e-06
In-116m Pu-241 Thermal 2.087130e-12 1.335770e-12
In-116m Pu-241 Thermal 9.815170e-13 6.281720e-13
In-116m Pu-241 Fast 4.479350e-11 2.866780e-11
In-116m Pu-241 Fast 2.152620e-11 1.377680e-11
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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)
-----------------------------------------------------------
In-116 U-235 Thermal 1.414550e-11 9.053100e-12
In-116 U-235 Fast 1.881800e-11 1.204350e-11
In-116 U-235 High 2.439340e-08 1.558870e-08
In-116 U-238 Fast 2.317470e-13 1.482640e-13
In-116 U-238 High 2.228430e-10 1.424650e-10
In-116 Pu-239 Thermal 4.084160e-10 2.613860e-10
In-116 Pu-239 Fast 5.150760e-10 3.296490e-10
In-116 Pu-239 High 8.174290e-07 5.228150e-07
In-116 Pu-241 Thermal 6.919500e-13 4.427770e-13
In-116 Pu-241 Fast 1.282080e-11 8.205290e-12
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In-116m U-235 Thermal 6.273220e-11 4.014860e-11
In-116m U-235 Thermal 2.006510e-11 1.284160e-11
In-116m U-235 Fast 9.734230e-11 6.229910e-11
In-116m U-235 Fast 3.159560e-11 2.022120e-11
In-116m U-235 High 2.076930e-07 1.329230e-07
In-116m U-235 High 6.969560e-08 4.453910e-08
In-116m U-238 Fast 1.198790e-12 7.672240e-13
In-116m U-238 Fast 3.891050e-13 2.489360e-13
In-116m U-238 High 1.897350e-09 1.214300e-09
In-116m U-238 High 6.366940e-10 4.070430e-10
In-116m Pu-239 Thermal 1.811240e-09 1.159190e-09
In-116m Pu-239 Thermal 5.793290e-10 3.707700e-10
In-116m Pu-239 Fast 2.664400e-09 1.705230e-09
In-116m Pu-239 Fast 8.648190e-10 5.534850e-10
In-116m Pu-239 High 6.959820e-06 4.454290e-06
In-116m Pu-239 High 2.335510e-06 1.493760e-06
In-116m Pu-241 Thermal 3.068650e-12 1.963940e-12
In-116m Pu-241 Thermal 9.815170e-13 6.280700e-13
In-116m Pu-241 Fast 6.631970e-11 4.244460e-11
In-116m Pu-241 Fast 2.152620e-11 1.377680e-11
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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