48-Cd-114
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)
113.903365086 ± 0.000000430 (amu) [mass excess = -90014.842 ± 0.401 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1446.445 ± 0.825 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cd-114.
Figures of cross sections, Cd-114: 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-113 (Z= 48, A=113), MT=102 (n,γ)
Cd-114 (Z= 48, A=114), MT= 2 (Elastic scattering)
Cd-114 (Z= 48, A=114), MT= 4 (Inelastic scattering)
Cd-116 (Z= 48, A=116), MT= 17 (n,3n)
In-115 (Z= 49, A=115), MT= 28 (n,np)
In-115 (Z= 49, A=115), MT=104 (n,d)
Sn-115 (Z= 50, A=115), MT=111 (n,2p)
Sn-116 (Z= 50, A=116), MT=106 (n,3He)
Sn-117 (Z= 50, A=117), MT=107 (n,α)
Sn-118 (Z= 50, A=118), 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)
-----------------------------------------------------------
Cd-114 U-235 Thermal 7.637840e-10 4.888210e-10
Cd-114 U-235 Fast 1.257410e-09 8.047390e-10
Cd-114 U-235 High 1.331830e-06 8.523690e-07
Cd-114 U-238 Fast 1.230460e-11 7.874940e-12
Cd-114 U-238 High 2.402620e-08 1.537680e-08
Cd-114 Pu-239 Thermal 2.219650e-09 1.420570e-09
Cd-114 Pu-239 Fast 6.478950e-09 4.146530e-09
Cd-114 Pu-239 High 3.862500e-05 2.472000e-05
Cd-114 Pu-241 Fast 2.028470e-10 1.298220e-10
-----------------------------------------------------------
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-114 U-235 Thermal 1.182010e-04 4.734420e-06
Cd-114 U-235 Fast 3.224990e-04 9.052850e-06
Cd-114 U-235 High 1.059070e-02 1.162890e-03
Cd-114 U-238 Fast 3.932010e-04 6.281470e-05
Cd-114 U-238 High 7.206060e-03 7.909640e-04
Cd-114 Pu-239 Thermal 6.027380e-04 1.687210e-05
Cd-114 Pu-239 Fast 9.430080e-04 1.885640e-05
Cd-114 Pu-239 High 1.257820e-02 1.382290e-03
Cd-114 Pu-241 Thermal 7.114560e-04 5.970360e-07
Cd-114 Pu-241 Fast 1.174160e-03 1.291320e-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