49-In-115
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
3.36244E+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)
114.903878776 ± 0.000000012 (amu) [mass excess = -89536.343 ± 0.012 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
497.490 ± 0.010 (keV)
Strong Gamma-rays from Decay of In-115 (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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497.37 0.05 B-
336.24 45.79 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- 4.41E+14 Y 25
B- 4.486 H 4
IT 4.486 H 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, In-115.
Figures of cross sections, In-115: 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
In-115 (Z= 49, A=115), MT= 2 (Elastic scattering)
In-115 (Z= 49, A=115), MT= 4 (Inelastic scattering)
Sn-115 (Z= 50, A=115), MT=103 (n,p)
Sn-116 (Z= 50, A=116), MT= 28 (n,np)
Sn-116 (Z= 50, A=116), MT=104 (n,d)
Sn-117 (Z= 50, A=117), MT= 32 (n,nd)
Sn-117 (Z= 50, A=117), MT= 41 (n,2np)
Sn-117 (Z= 50, A=117), 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-115 U-235 Thermal 1.631140e-12 1.043940e-12
In-115 U-235 Fast 1.820810e-12 1.165320e-12
In-115 U-235 High 1.008380e-08 6.453590e-09
In-115 U-238 Fast 9.654820e-15 6.179070e-15
In-115 U-238 High 9.191930e-11 5.882840e-11
In-115 Pu-239 Thermal 1.412660e-11 9.041010e-12
In-115 Pu-239 Fast 4.982870e-11 3.189030e-11
In-115 Pu-239 High 1.058290e-06 6.773080e-07
In-115 Pu-241 Fast 6.177120e-13 3.953350e-13
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In-115m U-235 Thermal 3.776540e-13 2.416990e-13
In-115m U-235 Fast 3.676640e-13 2.353050e-13
In-115m U-235 High 1.271830e-09 8.139700e-10
In-115m U-238 High 1.159340e-11 7.419820e-12
In-115m Pu-239 Thermal 3.270680e-12 2.093230e-12
In-115m Pu-239 Fast 1.006160e-11 6.439420e-12
In-115m Pu-239 High 1.334790e-07 8.542630e-08
In-115m Pu-241 Fast 1.247300e-13 7.982730e-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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In-115 U-235 Thermal 1.196470e-04 5.221450e-06
In-115 U-235 Fast 3.219340e-04 1.413950e-05
In-115 U-235 High 1.057640e-02 3.165740e-04
In-115 U-238 Fast 3.578820e-04 8.726650e-06
In-115 U-238 High 8.171670e-03 3.483350e-04
In-115 Pu-239 Thermal 4.056010e-04 2.539500e-05
In-115 Pu-239 Fast 7.750200e-04 3.346470e-05
In-115 Pu-239 High 1.212640e-02 7.551620e-04
In-115 Pu-241 Thermal 3.627070e-04 5.242730e-06
In-115 Pu-241 Fast 1.037330e-03 1.169340e-04
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In-115m U-235 Thermal 1.192020e-04 7.743030e-06
In-115m U-235 Fast 3.206930e-04 1.320000e-05
In-115m U-235 High 7.137950e-03 8.230340e-04
In-115m U-238 Fast 3.564950e-04 1.211270e-05
In-115m U-238 High 8.140090e-03 4.202990e-04
In-115m Pu-239 Thermal 4.040220e-04 2.692100e-05
In-115m Pu-239 Fast 7.719640e-04 3.906010e-05
In-115m Pu-239 High 1.195170e-02 1.002860e-03
In-115m Pu-241 Thermal 3.613010e-04 1.197150e-05
In-115m Pu-241 Fast 1.033330e-03 2.323980e-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