50-Sn-122
Spin
Level energy(keV) Spin & Parity
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ground state 0+
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)
121.903443774 ± 0.000002576 (amu) [mass excess = -89941.545 ± 2.400 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1607.921 ± 3.540 (keV)
Strong Gamma-rays from Decay of Sn-122 (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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281.0 -- IT
1105.4 -- IT
1140.5 -- 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(%). ]
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-122.
Figures of cross sections, Sn-122: 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
Sn-122 (Z= 50, A=122), MT= 2 (Elastic scattering)
Sn-122 (Z= 50, A=122), MT= 4 (Inelastic scattering)
Sn-123 (Z= 50, A=123), MT= 16 (n,2n)
Sn-124 (Z= 50, A=124), MT= 17 (n,3n)
Sb-123 (Z= 51, A=123), MT= 28 (n,np)
Sb-123 (Z= 51, A=123), MT=104 (n,d)
Sb-124 (Z= 51, A=124), MT= 32 (n,nd)
Sb-124 (Z= 51, A=124), MT=105 (n,t)
Sb-125 (Z= 51, A=125), MT= 33 (n,nt)
Te-125 (Z= 52, A=125), MT=107 (n,α)
Te-126 (Z= 52, A=126), 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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Sn-122 U-235 Thermal 3.644190e-06 2.332280e-06
Sn-122 U-235 Fast 1.079770e-05 6.910530e-06
Sn-122 U-235 High 1.682410e-04 1.076740e-04
Sn-122 U-238 Fast 5.231950e-07 3.348450e-07
Sn-122 U-238 High 7.828520e-06 5.010250e-06
Sn-122 Pu-239 Thermal 5.264180e-05 3.369070e-05
Sn-122 Pu-239 Fast 9.172520e-05 5.870410e-05
Sn-122 Pu-239 High 1.157480e-03 7.407870e-04
Sn-122 Pu-241 Thermal 3.760610e-06 2.406790e-06
Sn-122 Pu-241 Fast 2.038470e-05 1.304620e-05
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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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Sn-122 U-235 Thermal 1.629510e-04 1.481190e-05
Sn-122 U-235 Fast 4.390870e-04 5.658070e-05
Sn-122 U-235 High 1.222140e-02 1.473160e-03
Sn-122 U-238 Fast 4.235900e-04 4.697440e-05
Sn-122 U-238 High 8.713440e-03 9.587600e-04
Sn-122 Pu-239 Thermal 5.197750e-04 8.147080e-05
Sn-122 Pu-239 Fast 8.136620e-04 1.385810e-04
Sn-122 Pu-239 High 1.627890e-02 2.335590e-03
Sn-122 Pu-241 Thermal 2.848650e-04 8.682100e-05
Sn-122 Pu-241 Fast 1.037910e-03 1.769010e-04
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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