47-Ag-108
Spin
Level energy(keV) Spin & Parity
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ground state 1+
1.09466E+02 6+
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)
107.905950346 ± 0.000002563 (amu) [mass excess = -87606.688 ± 2.388 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1645.863 ± 2.640 (keV)
Strong Gamma-rays from Decay of Ag-108 (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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433.94 90.48 EC
614.28 89.84 EC
722.91 90.84 EC
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632.98 1.76 B-
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30.38 -- IT
79.13 6.63 IT
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433.96 0.5 EC
618.86 0.26 EC
1007.22 0.01 EC
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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- 2.382 M 11
EC 438 Y 9
EC 2.382 M 11
IT 438 Y 9
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Ag-107 (Z= 47, A=107), MT=102 (n,γ)
Ag-109 (Z= 47, A=109), MT= 16 (n,2n)
Ag-110 (Z= 47, A=110), MT= 17 (n,3n)
Cd-108 (Z= 48, A=108), MT=103 (n,p)
Cd-110 (Z= 48, A=110), MT= 32 (n,nd)
Cd-110 (Z= 48, A=110), MT=105 (n,t)
Sn-112 (Z= 50, A=112), MT=112 (n,pα)
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-108 U-235 High 2.501230e-11 1.600790e-11
Ag-108 U-238 High 1.078120e-13 6.900000e-14
Ag-108 Pu-239 Thermal 1.243640e-10 7.959300e-11
Ag-108 Pu-239 Fast 2.023070e-10 1.294770e-10
Ag-108 Pu-239 High 5.415410e-08 3.465860e-08
Ag-108 Pu-241 Thermal 9.599460e-13 6.143650e-13
Ag-108 Pu-241 Fast 6.694970e-12 4.284780e-12
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Ag-108m U-235 High 1.131770e-10 7.243340e-11
Ag-108m U-238 High 4.878360e-13 3.122150e-13
Ag-108m Pu-239 Thermal 2.915690e-10 1.866040e-10
Ag-108m Pu-239 Fast 5.525700e-10 3.536450e-10
Ag-108m Pu-239 High 2.450400e-07 1.568260e-07
Ag-108m Pu-241 Thermal 2.250570e-12 1.440370e-12
Ag-108m Pu-241 Fast 1.828620e-11 1.170320e-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)
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Ag-108 U-235 High 3.485870e-11 2.020190e-11
Ag-108 U-238 High 1.502540e-13 8.710140e-14
Ag-108 Pu-239 Thermal 1.497310e-10 9.147430e-11
Ag-108 Pu-239 Fast 2.503810e-10 1.512800e-10
Ag-108 Pu-239 High 7.547260e-08 4.376370e-08
Ag-108 Pu-241 Thermal 1.155750e-12 7.058840e-13
Ag-108 Pu-241 Fast 8.285870e-12 5.008850e-12
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Ag-108m U-235 High 1.131770e-10 7.232610e-11
Ag-108m U-238 High 4.878360e-13 3.118770e-13
Ag-108m Pu-239 Thermal 2.915690e-10 1.866040e-10
Ag-108m Pu-239 Fast 5.525700e-10 3.536450e-10
Ag-108m Pu-239 High 2.450400e-07 1.567240e-07
Ag-108m Pu-241 Thermal 2.250570e-12 1.440130e-12
Ag-108m Pu-241 Fast 1.828620e-11 1.170320e-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