46-Pd-108
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)
107.903891640 ± 0.000001191 (amu) [mass excess = -89524.361 ± 1.110 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1917.673 ± 2.634 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Pd-108.
Figures of cross sections, Pd-108: 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-107 (Z= 46, A=107), MT=102 (n,γ)
Pd-108 (Z= 46, A=108), MT= 2 (Elastic scattering)
Pd-108 (Z= 46, A=108), MT= 4 (Inelastic scattering)
Pd-110 (Z= 46, A=110), MT= 17 (n,3n)
Ag-109 (Z= 47, A=109), MT= 28 (n,np)
Ag-109 (Z= 47, A=109), MT=104 (n,d)
Ag-110 (Z= 47, A=110), MT= 32 (n,nd)
Ag-110 (Z= 47, A=110), MT= 41 (n,2np)
Ag-110 (Z= 47, A=110), MT=105 (n,t)
Ag-111 (Z= 47, A=111), MT= 33 (n,nt)
Cd-110 (Z= 48, A=110), MT=106 (n,3He)
Cd-111 (Z= 48, A=111), MT=107 (n,α)
Cd-112 (Z= 48, A=112), 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-108 U-235 High 3.624970e-07 2.319980e-07
Pd-108 U-238 High 8.879670e-09 5.682980e-09
Pd-108 Pu-239 Thermal 2.879540e-06 1.842910e-06
Pd-108 Pu-239 Fast 4.339290e-06 2.777150e-06
Pd-108 Pu-239 High 8.072230e-05 5.166230e-05
Pd-108 Pu-241 Thermal 1.220200e-07 7.809260e-08
Pd-108 Pu-241 Fast 5.685720e-07 3.638860e-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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Pd-108 U-235 Thermal 5.405300e-04 7.224150e-07
Pd-108 U-235 Fast 1.305740e-03 2.412710e-06
Pd-108 U-235 High 1.180150e-02 1.295950e-03
Pd-108 U-238 Fast 6.017140e-03 2.904330e-06
Pd-108 U-238 High 1.224280e-02 1.956030e-03
Pd-108 Pu-239 Thermal 2.163900e-02 8.655720e-04
Pd-108 Pu-239 Fast 2.002580e-02 1.602190e-03
Pd-108 Pu-239 High 2.400200e-02 2.638080e-03
Pd-108 Pu-241 Thermal 3.771070e-02 3.015720e-03
Pd-108 Pu-241 Fast 3.539870e-02 3.896210e-03
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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