47-Ag-113
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 1/2-
4.36000E+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)
112.906572893 ± 0.000017870 (amu) [mass excess = -87026.789 ± 16.646 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2016.462 ± 16.641 (keV)
Strong Gamma-rays from Decay of Ag-113 (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
----------------------------------------------------------
258.8 1.64 B-
298.6 10. B-
316.3 1.34 B-
----------------------------------------------------------
298.3 10.14 B-
316.1 17.64 B-
392.3 11.11 B-
43.6 0.41 IT
----------------------------------------------------------
*: 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- 5.37 H 5
B- 68.7 S 50
IT 68.7 S 16
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Cd-113 (Z= 48, A=113), MT=103 (n,p)
Cd-114 (Z= 48, A=114), MT= 28 (n,np)
Cd-114 (Z= 48, A=114), MT=104 (n,d)
In-115 (Z= 49, A=115), MT=106 (n,3He)
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)
-----------------------------------------------------------
Ag-113 U-235 Thermal 5.526650e-09 3.537050e-09
Ag-113 U-235 Fast 7.654200e-09 4.898690e-09
Ag-113 U-235 High 3.209910e-06 2.054350e-06
Ag-113 U-238 Fast 1.757680e-10 1.124920e-10
Ag-113 U-238 High 1.884700e-07 1.206210e-07
Ag-113 Pu-239 Thermal 1.849750e-12 1.183840e-12
Ag-113 Pu-239 Fast 2.118930e-12 1.356120e-12
Ag-113 Pu-239 High 3.986640e-05 2.551450e-05
Ag-113 Pu-241 Thermal 2.722950e-13 1.742690e-13
Ag-113 Pu-241 Fast 8.521450e-13 5.453730e-13
-----------------------------------------------------------
Ag-113m U-235 Thermal 3.602710e-08 2.305740e-08
Ag-113m U-235 Fast 5.721190e-08 3.661560e-08
Ag-113m U-235 High 3.847730e-05 2.462540e-05
Ag-113m U-238 Fast 1.313790e-09 8.408240e-10
Ag-113m U-238 High 2.259200e-06 1.445890e-06
Ag-113m Pu-239 Thermal 1.205810e-11 7.717160e-12
Ag-113m Pu-239 Fast 1.583810e-11 1.013640e-11
Ag-113m Pu-239 High 4.778790e-04 3.058430e-04
Ag-113m Pu-241 Thermal 1.775040e-12 1.136020e-12
Ag-113m Pu-241 Fast 6.369420e-12 4.076430e-12
-----------------------------------------------------------
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-113 U-235 Thermal 1.418130e-04 1.597270e-05
Ag-113 U-235 Fast 3.254530e-04 4.543820e-05
Ag-113 U-235 High 1.091510e-02 1.559220e-03
Ag-113 U-238 Fast 4.612930e-04 1.060830e-04
Ag-113 U-238 High 9.152520e-03 1.048880e-03
Ag-113 Pu-239 Thermal 8.165080e-04 8.668470e-05
Ag-113 Pu-239 Fast 1.276410e-03 1.571560e-04
Ag-113 Pu-239 High 1.278160e-02 3.914780e-03
Ag-113 Pu-241 Thermal 1.519490e-03 1.728720e-04
Ag-113 Pu-241 Fast 2.130800e-03 8.891780e-04
-----------------------------------------------------------
Ag-113m U-235 Thermal 3.602710e-08 3.962990e-09
Ag-113m U-235 Fast 5.721190e-08 2.574540e-08
Ag-113m U-235 High 3.847730e-05 1.231280e-05
Ag-113m U-238 Fast 1.313790e-09 5.912040e-10
Ag-113m U-238 High 2.259200e-06 1.016640e-06
Ag-113m Pu-239 Thermal 1.205810e-11 5.426140e-12
Ag-113m Pu-239 Fast 1.583810e-11 7.127150e-12
Ag-113m Pu-239 High 4.778790e-04 2.150460e-04
Ag-113m Pu-241 Thermal 1.775040e-12 7.987650e-13
Ag-113m Pu-241 Fast 6.369420e-12 2.866240e-12
-----------------------------------------------------------
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