46-Pd-106
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)
105.903480426 ± 0.000001187 (amu) [mass excess = -89907.404 ± 1.106 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2965.142 ± 2.817 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Pd-106.
Figures of cross sections, Pd-106: 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
Pd-105 (Z= 46, A=105), MT=102 (n,γ)
Pd-106 (Z= 46, A=106), MT= 2 (Elastic scattering)
Pd-106 (Z= 46, A=106), MT= 4 (Inelastic scattering)
Pd-107 (Z= 46, A=107), MT= 16 (n,2n)
Pd-108 (Z= 46, A=108), MT= 17 (n,3n)
Ag-107 (Z= 47, A=107), MT= 28 (n,np)
Ag-107 (Z= 47, A=107), MT=104 (n,d)
Ag-109 (Z= 47, A=109), MT= 33 (n,nt)
Cd-108 (Z= 48, A=108), MT=106 (n,3He)
Cd-110 (Z= 48, A=110), 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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Pd-106 U-235 High 2.152950e-09 1.377880e-09
Pd-106 U-238 High 2.512740e-11 1.608150e-11
Pd-106 Pu-239 Thermal 9.148560e-09 5.855080e-09
Pd-106 Pu-239 Fast 1.529750e-08 9.790420e-09
Pd-106 Pu-239 High 2.791810e-06 1.786760e-06
Pd-106 Pu-241 Thermal 8.061300e-11 5.159240e-11
Pd-106 Pu-241 Fast 2.917810e-10 1.867400e-10
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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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Pd-106 U-235 Thermal 4.008720e-03 6.758140e-06
Pd-106 U-235 Fast 5.314650e-03 9.294600e-06
Pd-106 U-235 High 1.613270e-02 6.448950e-04
Pd-106 U-238 Fast 2.493380e-02 3.635140e-05
Pd-106 U-238 High 2.463620e-02 6.931720e-04
Pd-106 Pu-239 Thermal 4.349800e-02 8.700390e-04
Pd-106 Pu-239 Fast 4.364310e-02 6.112590e-04
Pd-106 Pu-239 High 3.579470e-02 2.861980e-03
Pd-106 Pu-241 Thermal 6.104550e-02 1.220810e-03
Pd-106 Pu-241 Fast 6.238620e-02 8.760480e-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