46-Pd-105
Spin
Level energy(keV) Spin & Parity
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ground state 5/2+
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)
104.905079626 ± 0.000001222 (amu) [mass excess = -88417.759 ± 1.139 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1346.930 ± 4.670 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Pd-105.
Figures of cross sections, Pd-105: 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-104 (Z= 46, A=104), MT=102 (n,γ)
Pd-105 (Z= 46, A=105), MT= 2 (Elastic scattering)
Pd-105 (Z= 46, A=105), MT= 4 (Inelastic scattering)
Pd-106 (Z= 46, A=106), MT= 16 (n,2n)
Pd-107 (Z= 46, A=107), MT= 17 (n,3n)
Ag-107 (Z= 47, A=107), MT= 32 (n,nd)
Ag-107 (Z= 47, A=107), MT= 41 (n,2np)
Ag-107 (Z= 47, A=107), MT=105 (n,t)
Cd-108 (Z= 48, A=108), MT=107 (n,α)
Sn-112 (Z= 50, A=112), MT=108 (n,2α)
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-105 U-235 High 1.522090e-10 9.741350e-11
Pd-105 U-238 Fast 3.751390e-09 1.200450e-09
Pd-105 U-238 High 1.922090e-12 1.230140e-12
Pd-105 Pu-239 Thermal 2.419620e-10 1.548560e-10
Pd-105 Pu-239 Fast 3.319460e-10 2.124450e-10
Pd-105 Pu-239 High 2.171410e-07 1.389700e-07
Pd-105 Pu-241 Thermal 8.531370e-13 5.460080e-13
Pd-105 Pu-241 Fast 2.578060e-12 1.649960e-12
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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-105 U-235 Thermal 9.581860e-03 5.973970e-05
Pd-105 U-235 Fast 1.188340e-02 7.974820e-05
Pd-105 U-235 High 1.868220e-02 7.498060e-04
Pd-105 U-238 Fast 4.019430e-02 6.505310e-04
Pd-105 U-238 High 3.200240e-02 4.766700e-04
Pd-105 Pu-239 Thermal 5.632240e-02 1.134600e-03
Pd-105 Pu-239 Fast 5.352490e-02 1.503490e-03
Pd-105 Pu-239 High 4.273280e-02 1.710020e-03
Pd-105 Pu-241 Thermal 6.053230e-02 1.713870e-03
Pd-105 Pu-241 Fast 6.555150e-02 3.960150e-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