47-Ag-110
Spin
Level energy(keV) Spin & Parity
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ground state 1+
1.17590E+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)
109.906110226 ± 0.000001404 (amu) [mass excess = -87457.761 ± 1.309 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2891.004 ± 1.289 (keV)
Strong Gamma-rays from Decay of Ag-110 (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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374. < 0.02 EC
657.5 4.5 B-
815.5 0.04 B-
1125.8 0.02 B-
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657.76 94.32 B-
884.68 72.72 B-
937.49 34.24 B-
1.16 -- IT
116.48 8.E-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- 249.76 D 4
B- 24.6 S 2
EC 24.6 S 2
IT 249.76 D 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ag-110M.
Figures of cross sections, Ag-110M: 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=102 (n,γ)
Ag-110 (Z= 47, A=110), MT= 2 (Elastic scattering)
Ag-110 (Z= 47, A=110), MT= 4 (Inelastic scattering)
Ag-111 (Z= 47, A=111), MT= 16 (n,2n)
Cd-110 (Z= 48, A=110), MT=103 (n,p)
Cd-111 (Z= 48, A=111), MT= 28 (n,np)
Cd-111 (Z= 48, A=111), MT=104 (n,d)
Cd-112 (Z= 48, A=112), MT= 32 (n,nd)
Cd-112 (Z= 48, A=112), MT=105 (n,t)
In-113 (Z= 49, A=113), MT=107 (n,α)
Sn-114 (Z= 50, A=114), 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-110 U-235 Fast 2.374940e-14 1.519960e-14
Ag-110 U-235 High 9.149420e-09 5.855630e-09
Ag-110 U-238 High 1.317310e-10 8.430730e-11
Ag-110 Pu-239 High 1.389170e-06 8.890690e-07
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Ag-110m U-235 Thermal 1.595740e-14 1.021280e-14
Ag-110m U-235 Fast 6.486770e-14 4.151530e-14
Ag-110m U-235 High 4.139990e-08 2.649590e-08
Ag-110m U-238 High 5.960630e-10 3.814800e-10
Ag-110m Pu-239 High 6.285810e-06 4.022920e-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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Ag-110 U-235 Thermal 2.170210e-16 1.388930e-16
Ag-110 U-235 Fast 2.463160e-14 1.576420e-14
Ag-110 U-235 High 9.712460e-09 6.215970e-09
Ag-110 U-238 High 1.398370e-10 8.933630e-11
Ag-110 Pu-239 High 1.474660e-06 9.437810e-07
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Ag-110m U-235 Thermal 1.595740e-14 1.021270e-14
Ag-110m U-235 Fast 6.486770e-14 4.151530e-14
Ag-110m U-235 High 4.139990e-08 2.645670e-08
Ag-110m U-238 High 5.960630e-10 3.810670e-10
Ag-110m Pu-239 High 6.285810e-06 4.020310e-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