47-Ag-109
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
8.80341E+01 7/2+
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)
108.904755282 ± 0.000001405 (amu) [mass excess = -88719.883 ± 1.309 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-215.521 ± 1.790 (keV)
Strong Gamma-rays from Decay of Ag-109 (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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88.03 3.7 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 39.6 S 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ag-109.
Figures of cross sections, Ag-109: 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
Ag-109 (Z= 47, A=109), MT= 2 (Elastic scattering)
Ag-109 (Z= 47, A=109), MT= 4 (Inelastic scattering)
Ag-110 (Z= 47, A=110), MT= 16 (n,2n)
Ag-111 (Z= 47, A=111), MT= 17 (n,3n)
Cd-110 (Z= 48, A=110), MT= 28 (n,np)
Cd-110 (Z= 48, A=110), MT=104 (n,d)
Cd-111 (Z= 48, A=111), MT= 32 (n,nd)
Cd-111 (Z= 48, A=111), MT=105 (n,t)
In-113 (Z= 49, A=113), 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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Ag-109 U-235 High 2.544480e-10 1.628470e-10
Ag-109 U-238 High 1.903980e-12 1.218540e-12
Ag-109 Pu-239 High 9.631250e-08 6.164000e-08
Ag-109 Pu-241 Thermal 2.460900e-11 1.574980e-11
Ag-109 Pu-241 Fast 2.287480e-10 1.463990e-10
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Ag-109m U-235 High 3.050070e-09 1.952050e-09
Ag-109m U-238 High 2.282300e-11 1.460670e-11
Ag-109m Pu-239 High 1.154500e-06 7.388790e-07
Ag-109m Pu-241 Thermal 1.604210e-10 1.026690e-10
Ag-109m Pu-241 Fast 1.709790e-09 1.094270e-09
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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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Ag-109 U-235 Thermal 3.112370e-04 9.711080e-07
Ag-109 U-235 Fast 8.124670e-04 2.986460e-06
Ag-109 U-235 High 1.173270e-02 7.507230e-03
Ag-109 U-238 Fast 2.518120e-03 3.301770e-06
Ag-109 U-238 High 1.121950e-02 7.180500e-03
Ag-109 Pu-239 Thermal 1.477270e-02 6.059180e-06
Ag-109 Pu-239 Fast 1.035880e-02 3.934840e-06
Ag-109 Pu-239 High 2.477130e-02 1.584920e-02
Ag-109 Pu-241 Thermal 2.586490e-02 1.655350e-02
Ag-109 Pu-241 Fast 2.350260e-02 1.504170e-02
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Ag-109m U-235 Thermal 3.110810e-04 9.677310e-07
Ag-109m U-235 Fast 8.120600e-04 2.996710e-06
Ag-109m U-235 High 1.172680e-02 7.503630e-03
Ag-109m U-238 Fast 2.516860e-03 3.351130e-06
Ag-109m U-238 High 1.121390e-02 7.176910e-03
Ag-109m Pu-239 Thermal 1.476540e-02 6.345100e-06
Ag-109m Pu-239 Fast 1.035360e-02 4.114580e-06
Ag-109m Pu-239 High 2.475880e-02 1.584180e-02
Ag-109m Pu-241 Thermal 2.585200e-02 1.654530e-02
Ag-109m Pu-241 Fast 2.349090e-02 1.503410e-02
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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