47-Ag-107
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
9.31250E+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)
106.905091611 ± 0.000002557 (amu) [mass excess = -88406.595 ± 2.382 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1416.347 ± 2.567 (keV)
Strong Gamma-rays from Decay of Ag-107 (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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93.12 4.67 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 44.3 S 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ag-107.
Figures of cross sections, Ag-107: 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-107 (Z= 47, A=107), MT= 2 (Elastic scattering)
Ag-107 (Z= 47, A=107), MT= 4 (Inelastic scattering)
Ag-109 (Z= 47, A=109), MT= 17 (n,3n)
Cd-108 (Z= 48, A=108), MT= 28 (n,np)
Cd-108 (Z= 48, A=108), MT=104 (n,d)
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-107 U-235 High 3.779720e-13 2.419020e-13
Ag-107 Pu-239 Thermal 1.289900e-12 8.255370e-13
Ag-107 Pu-239 Fast 2.439850e-12 1.561500e-12
Ag-107 Pu-239 High 3.367080e-09 2.154930e-09
Ag-107 Pu-241 Fast 2.599940e-14 1.663960e-14
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Ag-107m U-235 High 4.530760e-12 2.899680e-12
Ag-107m U-238 High 1.025640e-14 6.564140e-15
Ag-107m Pu-239 Thermal 8.408570e-12 5.381480e-12
Ag-107m Pu-239 Fast 1.823680e-11 1.167160e-11
Ag-107m Pu-239 High 4.036130e-08 2.583120e-08
Ag-107m Pu-241 Thermal 2.089810e-14 1.337480e-14
Ag-107m Pu-241 Fast 1.943350e-13 1.243740e-13
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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-107 U-235 Thermal 1.457600e-03 4.321690e-06
Ag-107 U-235 Fast 3.007820e-03 1.544180e-05
Ag-107 U-235 High 1.282460e-02 1.414160e-03
Ag-107 U-238 Fast 1.433200e-02 1.267590e-04
Ag-107 U-238 High 1.678290e-02 1.609420e-04
Ag-107 Pu-239 Thermal 3.328650e-02 1.332080e-03
Ag-107 Pu-239 Fast 3.219870e-02 1.932650e-03
Ag-107 Pu-239 High 2.863610e-02 3.148540e-03
Ag-107 Pu-241 Thermal 4.879730e-02 6.585200e-05
Ag-107 Pu-241 Fast 4.898330e-02 5.397980e-03
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Ag-107m U-235 High 4.530760e-12 2.895390e-12
Ag-107m U-238 High 1.025640e-14 6.557030e-15
Ag-107m Pu-239 Thermal 8.408570e-12 5.381480e-12
Ag-107m Pu-239 Fast 1.823680e-11 1.167160e-11
Ag-107m Pu-239 High 4.036130e-08 2.581450e-08
Ag-107m Pu-241 Thermal 2.089810e-14 1.337480e-14
Ag-107m Pu-241 Fast 1.943350e-13 1.243740e-13
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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