49-In-113
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
3.91691E+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)
112.904061839 ± 0.000000914 (amu) [mass excess = -89365.821 ± 0.852 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1037.581 ± 1.696 (keV)
Strong Gamma-rays from Decay of In-113 (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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391.70 64.94 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
IT 1.6579 H 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, In-113.
Figures of cross sections, In-113: 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-113 (Z= 49, A=113), MT= 2 (Elastic scattering)
In-113 (Z= 49, A=113), MT= 4 (Inelastic scattering)
In-115 (Z= 49, A=115), MT= 17 (n,3n)
Sn-114 (Z= 50, A=114), MT= 28 (n,np)
Sn-114 (Z= 50, A=114), MT=104 (n,d)
Sn-115 (Z= 50, A=115), MT= 32 (n,nd)
Sn-115 (Z= 50, A=115), MT= 41 (n,2np)
Sn-115 (Z= 50, A=115), 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-113 U-235 High 2.857060e-11 1.828520e-11
In-113 U-238 High 4.684860e-14 2.998310e-14
In-113 Pu-239 High 1.128490e-08 7.222350e-09
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In-113m U-235 High 3.603500e-12 2.306240e-12
In-113m Pu-239 High 1.423320e-09 9.109270e-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-113 U-235 Thermal 1.418260e-04 2.141750e-07
In-113 U-235 Fast 3.254740e-04 6.633350e-07
In-113 U-235 High 1.092900e-02 8.731780e-04
In-113 U-238 Fast 4.612930e-04 1.804150e-07
In-113 U-238 High 9.153340e-03 5.486940e-04
In-113 Pu-239 Thermal 8.165080e-04 1.216540e-07
In-113 Pu-239 Fast 1.276410e-03 1.864970e-07
In-113 Pu-239 High 1.296110e-02 1.424810e-03
In-113 Pu-241 Thermal 1.519490e-03 2.452870e-07
In-113 Pu-241 Fast 2.130800e-03 1.612350e-06
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In-113m U-235 High 3.603500e-12 2.302820e-12
In-113m Pu-239 High 1.425550e-09 9.103420e-10
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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