44-Ru-103
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
2.38200E+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)
102.906318627 ± 0.000001165 (amu) [mass excess = -87263.637 ± 1.086 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
764.415 ± 2.185 (keV)
Strong Gamma-rays from Decay of Ru-103 (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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497.08 91. B-
557.06 0.84 B-
610.33 5.76 B-
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2.7 ? 0.31 IT
210.7 91. IT
213.4 5.1 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- 39.247 D 3
IT 1.69 MS 7
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ru-103.
Figures of cross sections, Ru-103: 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-102 (Z= 44, A=102), MT=102 (n,γ)
Ru-103 (Z= 44, A=103), MT= 2 (Elastic scattering)
Ru-103 (Z= 44, A=103), MT= 4 (Inelastic scattering)
Ru-104 (Z= 44, A=104), MT= 16 (n,2n)
Ru-105 (Z= 44, A=105), MT= 17 (n,3n)
Rh-103 (Z= 45, A=103), MT=103 (n,p)
Rh-105 (Z= 45, A=105), MT= 32 (n,nd)
Rh-105 (Z= 45, A=105), MT=105 (n,t)
Pd-104 (Z= 46, A=104), MT=111 (n,2p)
Pd-105 (Z= 46, A=105), MT=106 (n,3He)
Pd-106 (Z= 46, A=106), MT=107 (n,α)
Pd-107 (Z= 46, A=107), MT= 22 (n,nα)
Ag-107 (Z= 47, A=107), MT=112 (n,pα)
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-103 U-235 Thermal 2.356240e-07 1.508000e-07
Ru-103 U-235 Fast 9.919520e-08 6.348490e-08
Ru-103 U-235 High 1.480030e-05 9.472180e-06
Ru-103 U-238 Fast 7.572820e-09 4.846610e-09
Ru-103 U-238 High 2.642880e-07 1.691440e-07
Ru-103 Pu-239 Thermal 1.264800e-05 8.094720e-06
Ru-103 Pu-239 Fast 1.292790e-05 8.273860e-06
Ru-103 Pu-239 High 1.919240e-04 1.228320e-04
Ru-103 Pu-241 Thermal 3.790610e-07 2.425990e-07
Ru-103 Pu-241 Fast 4.576560e-07 2.929000e-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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Ru-103 U-235 Thermal 3.028690e-02 4.249220e-04
Ru-103 U-235 Fast 3.239800e-02 4.559920e-04
Ru-103 U-235 High 3.212970e-02 9.010780e-04
Ru-103 U-238 Fast 6.268170e-02 8.814480e-04
Ru-103 U-238 High 4.621080e-02 9.246570e-04
Ru-103 Pu-239 Thermal 6.999100e-02 1.399620e-03
Ru-103 Pu-239 Fast 6.833460e-02 9.571290e-04
Ru-103 Pu-239 High 5.214830e-02 3.125480e-03
Ru-103 Pu-241 Thermal 6.790690e-02 4.068470e-03
Ru-103 Pu-241 Fast 6.514150e-02 3.905300e-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