45-Rh-105
Spin
Level energy(keV) Spin & Parity
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ground state 7/2+
1.29570E+02 1/2-
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)
104.905688549 ± 0.000002694 (amu) [mass excess = -87850.550 ± 2.510 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
567.208 ± 2.352 (keV)
Strong Gamma-rays from Decay of Rh-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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280.1 0.17 B-
306.1 5.1 B-
318.9 19.1 B-
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129.57 -- 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- 35.36 H 6
IT 40 S AP
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Rh-105.
Figures of cross sections, Rh-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
Rh-105 (Z= 45, A=105), MT= 2 (Elastic scattering)
Rh-105 (Z= 45, A=105), MT= 4 (Inelastic scattering)
Pd-105 (Z= 46, A=105), MT=103 (n,p)
Pd-106 (Z= 46, A=106), MT= 28 (n,np)
Pd-106 (Z= 46, A=106), MT=104 (n,d)
Pd-107 (Z= 46, A=107), MT= 32 (n,nd)
Pd-107 (Z= 46, A=107), MT= 41 (n,2np)
Pd-107 (Z= 46, A=107), MT=105 (n,t)
Ag-107 (Z= 47, A=107), MT=106 (n,3He)
Ag-109 (Z= 47, A=109), MT= 22 (n,nα)
Ag-110 (Z= 47, A=110), MT= 24 (n,2nα)
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-105 U-235 Fast 6.161280e-10 1.971610e-10
Rh-105 U-235 High 4.099130e-08 1.311720e-08
Rh-105 U-238 Fast 4.471640e-10 2.861850e-10
Rh-105 U-238 High 7.872530e-09 2.519210e-09
Rh-105 Pu-239 Thermal 1.375710e-06 8.804560e-07
Rh-105 Pu-239 Fast 1.633200e-06 1.045250e-06
Rh-105 Pu-239 High 7.251170e-05 4.640750e-05
Rh-105 Pu-241 Thermal 3.080080e-08 1.971250e-08
Rh-105 Pu-241 Fast 6.430240e-08 4.115350e-08
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Rh-105m U-235 Fast 8.242990e-11 5.275510e-11
Rh-105m U-235 High 3.419640e-09 2.188570e-09
Rh-105m U-238 Fast 5.982470e-11 3.828780e-11
Rh-105m U-238 High 6.567550e-10 4.203250e-10
Rh-105m Pu-239 Thermal 2.110370e-07 1.350640e-07
Rh-105m Pu-239 Fast 2.185000e-07 1.398410e-07
Rh-105m Pu-239 High 6.049190e-06 3.871480e-06
Rh-105m Pu-241 Thermal 4.724930e-09 3.023950e-09
Rh-105m Pu-241 Fast 8.602810e-09 5.505800e-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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Rh-105 U-235 Thermal 9.581860e-03 5.973970e-05
Rh-105 U-235 Fast 1.188340e-02 3.443290e-04
Rh-105 U-235 High 1.868220e-02 1.123890e-03
Rh-105 U-238 Fast 4.019430e-02 8.706410e-04
Rh-105 U-238 High 3.200240e-02 6.619590e-04
Rh-105 Pu-239 Thermal 5.632240e-02 1.134600e-03
Rh-105 Pu-239 Fast 5.352490e-02 1.503490e-03
Rh-105 Pu-239 High 4.273260e-02 2.564920e-03
Rh-105 Pu-241 Thermal 6.053230e-02 1.713870e-03
Rh-105 Pu-241 Fast 6.555150e-02 7.247270e-03
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Rh-105m U-235 Thermal 2.730830e-03 1.275900e-04
Rh-105m U-235 Fast 3.386760e-03 2.492370e-04
Rh-105m U-235 High 5.324430e-03 1.193460e-03
Rh-105m U-238 Fast 1.145540e-02 6.008070e-04
Rh-105m U-238 High 9.120690e-03 5.007540e-04
Rh-105m Pu-239 Thermal 1.605170e-02 1.016710e-03
Rh-105m Pu-239 Fast 1.525430e-02 9.713100e-04
Rh-105m Pu-239 High 1.216250e-02 1.950730e-03
Rh-105m Pu-241 Thermal 1.725170e-02 1.300980e-03
Rh-105m Pu-241 Fast 1.868220e-02 2.985160e-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