44-Ru-105
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
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)
104.907747645 ± 0.000002756 (amu) [mass excess = -85932.515 ± 2.568 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1918.035 ± 2.876 (keV)
Strong Gamma-rays from Decay of Ru-105 (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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469.37 17.55 B-
676.36 15.66 B-
724.30 47.3 B-
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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- 4.44 H 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ru-105.
Figures of cross sections, Ru-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
Ru-104 (Z= 44, A=104), MT=102 (n,γ)
Ru-105 (Z= 44, A=105), MT= 2 (Elastic scattering)
Ru-105 (Z= 44, A=105), MT= 4 (Inelastic scattering)
Ru-106 (Z= 44, A=106), MT= 16 (n,2n)
Rh-105 (Z= 45, A=105), MT=103 (n,p)
Pd-107 (Z= 46, A=107), MT=106 (n,3He)
Pd-108 (Z= 46, A=108), MT=107 (n,α)
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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Ru-105 U-235 Thermal 1.108230e-09 7.092710e-10
Ru-105 U-235 Fast 1.007920e-09 6.450680e-10
Ru-105 U-235 High 9.924610e-05 6.351740e-05
Ru-105 U-238 Fast 3.601340e-06 2.304850e-06
Ru-105 U-238 High 2.822070e-05 1.806130e-05
Ru-105 Pu-239 Thermal 4.543880e-04 2.908090e-04
Ru-105 Pu-239 Fast 8.866460e-04 5.674540e-04
Ru-105 Pu-239 High 3.375140e-03 2.160090e-03
Ru-105 Pu-241 Thermal 8.909430e-05 5.702040e-05
Ru-105 Pu-241 Fast 1.399850e-04 8.959020e-05
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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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Ru-105 U-235 Thermal 9.581860e-03 5.815720e-04
Ru-105 U-235 Fast 1.188340e-02 7.222030e-04
Ru-105 U-235 High 1.868220e-02 2.995530e-03
Ru-105 U-238 Fast 4.019430e-02 1.178250e-03
Ru-105 U-238 High 3.200240e-02 9.139610e-04
Ru-105 Pu-239 Thermal 5.632090e-02 1.584380e-03
Ru-105 Pu-239 Fast 5.352310e-02 2.146020e-03
Ru-105 Pu-239 High 4.265400e-02 6.827220e-03
Ru-105 Pu-241 Thermal 6.053230e-02 3.650710e-03
Ru-105 Pu-241 Fast 6.555150e-02 1.053730e-02
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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