48-Cd-112
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)
111.902762868 ± 0.000000595 (amu) [mass excess = -90575.805 ± 0.555 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2584.734 ± 4.243 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cd-112.
Figures of cross sections, Cd-112: 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
Cd-111 (Z= 48, A=111), MT=102 (n,γ)
Cd-112 (Z= 48, A=112), MT= 2 (Elastic scattering)
Cd-112 (Z= 48, A=112), MT= 4 (Inelastic scattering)
Cd-113 (Z= 48, A=113), MT= 16 (n,2n)
Cd-114 (Z= 48, A=114), MT= 17 (n,3n)
In-113 (Z= 49, A=113), MT= 28 (n,np)
In-113 (Z= 49, A=113), MT=104 (n,d)
Sn-114 (Z= 50, A=114), MT=106 (n,3He)
Sn-115 (Z= 50, A=115), MT=107 (n,α)
Sn-116 (Z= 50, A=116), MT= 22 (n,nα)
Sn-117 (Z= 50, A=117), MT= 24 (n,2nα)
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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Cd-112 U-235 Thermal 1.058320e-11 3.386610e-12
Cd-112 U-235 Fast 1.147630e-13 7.344840e-14
Cd-112 U-235 High 1.121530e-09 3.588920e-10
Cd-112 U-238 High 4.985430e-11 3.190670e-11
Cd-112 Pu-239 High 1.170760e-06 7.492860e-07
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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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Cd-112 U-235 Thermal 1.302170e-04 5.220800e-06
Cd-112 U-235 Fast 3.763360e-04 7.582650e-06
Cd-112 U-235 High 1.077410e-02 8.608000e-04
Cd-112 U-238 Fast 5.592180e-04 2.043090e-07
Cd-112 U-238 High 1.033820e-02 2.893720e-04
Cd-112 Pu-239 Thermal 1.284890e-03 1.745070e-07
Cd-112 Pu-239 Fast 1.888980e-03 2.617020e-07
Cd-112 Pu-239 High 1.393210e-02 8.354310e-04
Cd-112 Pu-241 Thermal 2.185220e-03 3.576280e-07
Cd-112 Pu-241 Fast 3.175470e-03 2.391170e-06
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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