48-Cd-113
Spin
Level energy(keV) Spin & Parity
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ground state 1/2+
2.63700E+02 11/2-
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)
112.904408133 ± 0.000000445 (amu) [mass excess = -89043.251 ± 0.415 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
322.571 ± 0.790 (keV)
Strong Gamma-rays from Decay of Cd-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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263.7 0.03 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- 8.04E15 Y 5
B- 14.1 Y 5
IT 14.1 Y 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cd-113.
Figures of cross sections, Cd-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
Cd-112 (Z= 48, A=112), MT=102 (n,γ)
Cd-113 (Z= 48, A=113), MT= 2 (Elastic scattering)
Cd-113 (Z= 48, A=113), MT= 4 (Inelastic scattering)
Cd-114 (Z= 48, A=114), MT= 16 (n,2n)
In-113 (Z= 49, A=113), MT=103 (n,p)
In-115 (Z= 49, A=115), MT= 32 (n,nd)
In-115 (Z= 49, A=115), MT=105 (n,t)
Sn-114 (Z= 50, A=114), MT=111 (n,2p)
Sn-115 (Z= 50, A=115), MT=106 (n,3He)
Sn-116 (Z= 50, A=116), MT=107 (n,α)
Sn-117 (Z= 50, A=117), 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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Cd-113 U-235 Thermal 2.632990e-12 1.685110e-12
Cd-113 U-235 Fast 3.564460e-12 2.281250e-12
Cd-113 U-235 High 1.666110e-08 1.066310e-08
Cd-113 U-238 Fast 1.599450e-14 1.023650e-14
Cd-113 U-238 High 1.989870e-10 1.273520e-10
Cd-113 Pu-239 High 1.033440e-06 6.614020e-07
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Cd-113m U-235 Thermal 8.619100e-12 5.516220e-12
Cd-113m U-235 Fast 1.349040e-11 8.633820e-12
Cd-113m U-235 High 1.032030e-07 6.605000e-08
Cd-113m U-238 Fast 6.053410e-14 3.874170e-14
Cd-113m U-238 High 1.232580e-09 7.888450e-10
Cd-113m Pu-239 High 6.401380e-06 4.096880e-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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Cd-113 U-235 Thermal 1.395600e-04 5.674760e-06
Cd-113 U-235 Fast 3.202740e-04 9.255790e-06
Cd-113 U-235 High 1.075450e-02 8.634080e-04
Cd-113 U-238 Fast 4.539230e-04 5.016180e-05
Cd-113 U-238 High 9.007100e-03 5.429940e-04
Cd-113 Pu-239 Thermal 8.034630e-04 3.617490e-06
Cd-113 Pu-239 Fast 1.256020e-03 5.660460e-06
Cd-113 Pu-239 High 1.275040e-02 2.944530e-03
Cd-113 Pu-241 Thermal 1.495210e-03 6.282470e-06
Cd-113 Pu-241 Fast 2.096750e-03 1.072740e-05
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Cd-113m U-235 Thermal 2.269010e-06 6.234400e-07
Cd-113m U-235 Fast 5.207260e-06 1.849000e-06
Cd-113m U-235 High 1.747440e-04 4.849050e-05
Cd-113m U-238 Fast 7.380690e-06 2.169440e-06
Cd-113m U-238 High 1.464420e-04 4.000960e-05
Cd-113m Pu-239 Thermal 1.306410e-05 3.514250e-06
Cd-113m Pu-239 Fast 2.042260e-05 5.482920e-06
Cd-113m Pu-239 High 2.109070e-04 9.016180e-05
Cd-113m Pu-241 Thermal 2.431180e-05 6.531770e-06
Cd-113m Pu-241 Fast 3.409280e-05 9.142760e-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