49-In-123
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state (9/2)+
3.27210E+02 (1/2)-
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)
122.910433718 ± 0.000021285 (amu) [mass excess = -83430.454 ± 19.827 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
4385.936 ± 19.839 (keV)
Strong Gamma-rays from Decay of In-123 (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
----------------------------------------------------------
125.76 ~*40000. B-
1170. *100. B-
3234. *122. B-
----------------------------------------------------------
618.8 2.5 B-
1019.7 30.72 B-
1130.5 60.48 B-
----------------------------------------------------------
*: 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- 47.4 S 4
B- 6.17 S 5
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Sn-123 (Z= 50, A=123), MT=103 (n,p)
Sn-124 (Z= 50, A=124), MT= 28 (n,np)
Sn-124 (Z= 50, A=124), MT=104 (n,d)
Sb-126 (Z= 51, A=126), MT=107 (n,α)
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)
-----------------------------------------------------------
In-123 U-235 Thermal 3.374170e-05 2.159470e-05
In-123 U-235 Fast 1.922360e-04 1.230310e-04
In-123 U-235 High 4.697520e-03 3.006420e-03
In-123 U-238 Fast 9.761330e-05 6.247250e-05
In-123 U-238 High 1.572290e-03 1.006260e-03
In-123 Pu-239 Thermal 1.948500e-04 1.247030e-04
In-123 Pu-239 Fast 3.361900e-04 2.151620e-04
In-123 Pu-239 High 8.406260e-03 5.380010e-03
In-123 Pu-241 Thermal 1.162570e-04 7.440410e-05
In-123 Pu-241 Fast 4.661270e-04 2.983210e-04
-----------------------------------------------------------
In-123m U-235 Thermal 7.812110e-06 4.999770e-06
In-123m U-235 Fast 3.881690e-05 2.484280e-05
In-123m U-235 High 5.924800e-04 3.791880e-04
In-123m U-238 Fast 1.971040e-05 1.261470e-05
In-123m U-238 High 1.983060e-04 1.269160e-04
In-123m Pu-239 Thermal 4.511300e-05 2.887230e-05
In-123m Pu-239 Fast 6.788450e-05 4.344610e-05
In-123m Pu-239 High 1.060250e-03 6.785600e-04
In-123m Pu-241 Thermal 2.691660e-05 1.722660e-05
In-123m Pu-241 Fast 9.412180e-05 6.023790e-05
-----------------------------------------------------------
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)
-----------------------------------------------------------
In-123 U-235 Thermal 6.587260e-05 1.515070e-05
In-123 U-235 Fast 2.402620e-04 1.537680e-04
In-123 U-235 High 6.548280e-03 2.946730e-03
In-123 U-238 Fast 1.979820e-04 1.267080e-04
In-123 U-238 High 3.868950e-03 1.741030e-03
In-123 Pu-239 Thermal 2.104820e-04 1.347090e-04
In-123 Pu-239 Fast 3.624870e-04 2.319910e-04
In-123 Pu-239 High 9.762730e-03 5.662150e-03
In-123 Pu-241 Thermal 1.474830e-04 9.438880e-05
In-123 Pu-241 Fast 5.694800e-04 3.644680e-04
-----------------------------------------------------------
In-123m U-235 Thermal 7.932930e-05 4.820100e-05
In-123m U-235 Fast 1.457140e-04 8.565150e-05
In-123m U-235 High 4.711920e-03 2.887940e-03
In-123m U-238 Fast 2.431110e-04 1.555910e-04
In-123m U-238 High 5.310230e-03 1.699270e-03
In-123m Pu-239 Thermal 7.990680e-05 4.307400e-05
In-123m Pu-239 Fast 1.264160e-04 6.819800e-05
In-123m Pu-239 High 4.079490e-03 2.409220e-03
In-123m Pu-241 Thermal 9.641940e-05 5.634740e-05
In-123m Pu-241 Fast 3.241660e-04 1.882770e-04
-----------------------------------------------------------
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