45-Rh-103
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
3.97550E+01 7/2+
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)
102.905497993 ± 0.000002610 (amu) [mass excess = -88028.052 ± 2.431 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-543.020 ± 0.797 (keV)
Strong Gamma-rays from Decay of Rh-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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39.76 0.07 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
IT 56.114 M 20
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Rh-103.
Figures of cross sections, Rh-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
Rh-103 (Z= 45, A=103), MT= 2 (Elastic scattering)
Rh-103 (Z= 45, A=103), MT= 4 (Inelastic scattering)
Rh-105 (Z= 45, A=105), MT= 17 (n,3n)
Pd-104 (Z= 46, A=104), MT= 28 (n,np)
Pd-104 (Z= 46, A=104), MT=104 (n,d)
Pd-105 (Z= 46, A=105), MT= 32 (n,nd)
Pd-105 (Z= 46, A=105), MT= 41 (n,2np)
Pd-105 (Z= 46, A=105), MT=105 (n,t)
Ag-107 (Z= 47, A=107), 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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Rh-103 U-235 Thermal 6.517260e-13 4.171050e-13
Rh-103 U-235 Fast 2.006580e-13 1.284210e-13
Rh-103 U-235 High 1.323900e-10 4.236500e-11
Rh-103 U-238 Fast 1.054130e-14 6.746430e-15
Rh-103 U-238 High 2.697930e-12 1.726680e-12
Rh-103 Pu-239 Thermal 3.408250e-10 2.181280e-10
Rh-103 Pu-239 Fast 3.002610e-10 1.921670e-10
Rh-103 Pu-239 High 5.677810e-08 3.633800e-08
Rh-103 Pu-241 Thermal 1.636170e-12 1.047150e-12
Rh-103 Pu-241 Fast 2.250930e-12 1.440590e-12
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Rh-103m U-235 Thermal 4.248470e-12 2.719020e-12
Rh-103m U-235 Fast 1.499830e-12 9.598920e-13
Rh-103m U-235 High 1.586960e-09 1.015660e-09
Rh-103m U-238 Fast 7.879200e-14 5.042690e-14
Rh-103m U-238 High 3.234020e-11 2.069770e-11
Rh-103m Pu-239 Thermal 2.221770e-09 1.421930e-09
Rh-103m Pu-239 Fast 2.244330e-09 1.436360e-09
Rh-103m Pu-239 High 6.806000e-07 4.355840e-07
Rh-103m Pu-241 Thermal 1.066580e-11 6.826120e-12
Rh-103m Pu-241 Fast 1.682470e-11 1.076780e-11
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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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Rh-103 U-235 Thermal 3.028690e-02 3.039190e-04
Rh-103 U-235 Fast 3.239800e-02 4.559920e-04
Rh-103 U-235 High 3.212970e-02 9.010780e-04
Rh-103 U-238 Fast 6.268170e-02 8.814480e-04
Rh-103 U-238 High 4.621080e-02 9.246570e-04
Rh-103 Pu-239 Thermal 6.999100e-02 1.399620e-03
Rh-103 Pu-239 Fast 6.833460e-02 9.571290e-04
Rh-103 Pu-239 High 5.214900e-02 2.084340e-03
Rh-103 Pu-241 Thermal 6.790690e-02 1.902540e-03
Rh-103 Pu-241 Fast 6.514150e-02 2.603930e-03
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Rh-103m U-235 Thermal 3.021120e-02 4.673890e-04
Rh-103m U-235 Fast 3.231700e-02 4.930330e-04
Rh-103m U-235 High 3.204940e-02 9.449530e-04
Rh-103m U-238 Fast 6.252500e-02 9.570480e-04
Rh-103m U-238 High 4.609530e-02 9.970620e-04
Rh-103m Pu-239 Thermal 6.981600e-02 1.496700e-03
Rh-103m Pu-239 Fast 6.816380e-02 1.098480e-03
Rh-103m Pu-239 High 5.201860e-02 3.127580e-03
Rh-103m Pu-241 Thermal 6.773710e-02 2.760320e-03
Rh-103m Pu-241 Fast 6.497860e-02 3.904580e-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