48-Cd-110
Spin
Level energy(keV) Spin & Parity
----------------------------------------
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)
109.903006606 ± 0.000000606 (amu) [mass excess = -90348.765 ± 0.564 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-3878.000 ± 11.547 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cd-110.
Figures of cross sections, Cd-110: 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-110 (Z= 48, A=110), MT= 2 (Elastic scattering)
Cd-110 (Z= 48, A=110), MT= 4 (Inelastic scattering)
Cd-111 (Z= 48, A=111), MT= 16 (n,2n)
Cd-112 (Z= 48, A=112), MT= 17 (n,3n)
Sn-112 (Z= 50, A=112), MT= 44 (n,n2p)
Sn-112 (Z= 50, A=112), MT=106 (n,3He)
Sn-112 (Z= 50, A=112), MT=115 (n,pd)
Sn-114 (Z= 50, A=114), MT= 22 (n,nα)
Sn-115 (Z= 50, A=115), 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)
-----------------------------------------------------------
Cd-110 U-235 High 1.001370e-11 6.408780e-12
Cd-110 U-238 High 2.372580e-14 1.518460e-14
Cd-110 Pu-239 High 1.180770e-08 7.556900e-09
-----------------------------------------------------------
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)
-----------------------------------------------------------
Cd-110 U-235 Thermal 1.595670e-14 1.021230e-14
Cd-110 U-235 Fast 8.854310e-14 1.560640e-16
Cd-110 U-235 High 5.053020e-08 3.225260e-08
Cd-110 U-238 High 7.273980e-10 4.652820e-10
Cd-110 Pu-239 High 7.682360e-06 4.908820e-06
-----------------------------------------------------------
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