47-Ag-111
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
5.98200E+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)
110.905295923 ± 0.000001634 (amu) [mass excess = -88216.279 ± 1.523 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1036.800 ± 1.414 (keV)
Strong Gamma-rays from Decay of Ag-111 (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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59.77 0.53 IT
171.28 0.09 B-
245.4 0.37 B-
620.1 0.09 B-
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96.75 0.12 B-
245.40 1.33 B-
342.13 6.68 B-
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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- 7.45 D 1
B- 64.8 S 8
IT 64.8 S 8
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ag-111.
Figures of cross sections, Ag-111: 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-110 (Z= 47, A=110), MT=102 (n,γ)
Ag-111 (Z= 47, A=111), MT= 2 (Elastic scattering)
Ag-111 (Z= 47, A=111), MT= 4 (Inelastic scattering)
Cd-111 (Z= 48, A=111), MT=103 (n,p)
Cd-112 (Z= 48, A=112), MT= 28 (n,np)
Cd-112 (Z= 48, A=112), MT=104 (n,d)
Cd-113 (Z= 48, A=113), MT= 32 (n,nd)
Cd-113 (Z= 48, A=113), MT=105 (n,t)
In-113 (Z= 49, A=113), MT=106 (n,3He)
In-115 (Z= 49, A=115), 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-111 U-235 Thermal 1.264150e-12 8.090550e-13
Ag-111 U-235 Fast 2.823810e-12 1.807230e-12
Ag-111 U-235 High 4.927820e-08 3.153810e-08
Ag-111 U-238 High 1.172450e-09 7.503650e-10
Ag-111 Pu-239 High 3.189100e-06 2.041020e-06
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Ag-111m U-235 Thermal 8.240710e-12 5.274060e-12
Ag-111m U-235 Fast 2.110680e-11 1.350840e-11
Ag-111m U-235 High 5.906990e-07 3.780470e-07
Ag-111m U-238 Fast 2.929330e-14 1.874770e-14
Ag-111m U-238 High 1.405420e-08 8.994650e-09
Ag-111m Pu-239 Thermal 2.834640e-14 1.814170e-14
Ag-111m Pu-239 Fast 3.377510e-14 2.161610e-14
Ag-111m Pu-239 High 3.822780e-05 2.446580e-05
Ag-111m Pu-241 Fast 9.342170e-15 5.978990e-15
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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)
-----------------------------------------------------------
Ag-111 U-235 Thermal 1.712450e-04 7.401970e-06
Ag-111 U-235 Fast 4.176640e-04 1.370970e-05
Ag-111 U-235 High 1.066480e-02 3.161200e-04
Ag-111 U-238 Fast 6.871470e-04 2.287850e-05
Ag-111 U-238 High 9.733890e-03 3.194220e-04
Ag-111 Pu-239 Thermal 2.936640e-03 1.444360e-05
Ag-111 Pu-239 Fast 3.542140e-03 1.734240e-05
Ag-111 Pu-239 High 1.535400e-02 1.236300e-03
Ag-111 Pu-241 Thermal 5.801900e-03 3.577070e-05
Ag-111 Pu-241 Fast 6.387660e-03 3.897680e-05
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Ag-111m U-235 Thermal 1.712350e-04 1.911940e-05
Ag-111m U-235 Fast 4.176380e-04 3.418060e-05
Ag-111m U-235 High 1.065990e-02 1.178750e-03
Ag-111m U-238 Fast 6.871130e-04 5.993620e-05
Ag-111m U-238 High 9.732970e-03 7.965190e-04
Ag-111m Pu-239 Thermal 2.936480e-03 2.350710e-04
Ag-111m Pu-239 Fast 3.541950e-03 2.126550e-04
Ag-111m Pu-239 High 1.529780e-02 3.513580e-03
Ag-111m Pu-241 Thermal 5.801610e-03 1.079780e-05
Ag-111m Pu-241 Fast 6.387340e-03 2.047660e-03
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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