46-Pd-107
Spin
Level energy(keV) Spin & Parity
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ground state 5/2+
2.14600E+02 11/2-
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)
106.905128195 ± 0.000001290 (amu) [mass excess = -88372.517 ± 1.202 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
34.078 ± 2.318 (keV)
Strong Gamma-rays from Decay of Pd-107 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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214.9 68.7 IT
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 6.5E+6 Y 3
IT 21.3 S 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Pd-107.
Figures of cross sections, Pd-107: 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-106 (Z= 46, A=106), MT=102 (n,γ)
Pd-107 (Z= 46, A=107), MT= 2 (Elastic scattering)
Pd-107 (Z= 46, A=107), MT= 4 (Inelastic scattering)
Pd-108 (Z= 46, A=108), MT= 16 (n,2n)
Ag-107 (Z= 47, A=107), MT=103 (n,p)
Ag-109 (Z= 47, A=109), MT= 32 (n,nd)
Ag-109 (Z= 47, A=109), MT= 41 (n,2np)
Ag-109 (Z= 47, A=109), MT=105 (n,t)
Ag-110 (Z= 47, A=110), MT= 33 (n,nt)
Cd-110 (Z= 48, A=110), MT=107 (n,α)
Cd-111 (Z= 48, A=111), 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-107 U-235 High 6.533150e-09 4.181220e-09
Pd-107 U-238 High 1.025650e-10 6.564170e-11
Pd-107 Pu-239 Thermal 6.768890e-08 4.332090e-08
Pd-107 Pu-239 Fast 1.023340e-07 6.549420e-08
Pd-107 Pu-239 High 4.791350e-06 3.066460e-06
Pd-107 Pu-241 Thermal 1.360460e-09 8.706940e-10
Pd-107 Pu-241 Fast 5.298240e-09 3.390870e-09
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Pd-107m U-235 High 2.413890e-08 1.544880e-08
Pd-107m U-238 High 3.789600e-10 2.425340e-10
Pd-107m Pu-239 Thermal 1.273800e-07 8.152350e-08
Pd-107m Pu-239 Fast 2.246120e-07 1.437520e-07
Pd-107m Pu-239 High 1.770320e-05 1.133010e-05
Pd-107m Pu-241 Thermal 2.560170e-09 1.638510e-09
Pd-107m Pu-241 Fast 1.162900e-08 7.442580e-09
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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-107 U-235 Thermal 1.457600e-03 4.321690e-06
Pd-107 U-235 Fast 3.007820e-03 1.544180e-05
Pd-107 U-235 High 1.282460e-02 1.414160e-03
Pd-107 U-238 Fast 1.433200e-02 1.267590e-04
Pd-107 U-238 High 1.678290e-02 1.029290e-03
Pd-107 Pu-239 Thermal 3.328650e-02 1.332080e-03
Pd-107 Pu-239 Fast 3.219870e-02 2.576860e-03
Pd-107 Pu-239 High 2.863600e-02 3.148550e-03
Pd-107 Pu-241 Thermal 4.879730e-02 3.909600e-03
Pd-107 Pu-241 Fast 4.898330e-02 5.397980e-03
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Pd-107m U-235 High 2.413890e-08 1.542600e-08
Pd-107m U-238 High 3.789600e-10 2.422710e-10
Pd-107m Pu-239 Thermal 1.273800e-07 8.152350e-08
Pd-107m Pu-239 Fast 2.246120e-07 1.437520e-07
Pd-107m Pu-239 High 1.770320e-05 1.132270e-05
Pd-107m Pu-241 Thermal 2.560170e-09 1.638250e-09
Pd-107m Pu-241 Fast 1.162900e-08 7.442580e-09
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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