59-Pr-143
Spin
Level energy(keV) Spin & Parity
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ground state 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)
142.910822796 ± 0.000002396 (amu) [mass excess = -83068.031 ± 2.232 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
934.108 ± 1.355 (keV)
Strong Gamma-rays from Decay of Pr-143 (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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742.10 1.E-06 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- 13.57 D 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Pr-143.
Figures of cross sections, Pr-143: 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
Pr-143 (Z= 59, A=143), MT= 2 (Elastic scattering)
Pr-143 (Z= 59, A=143), MT= 4 (Inelastic scattering)
Nd-143 (Z= 60, A=143), MT=103 (n,p)
Nd-144 (Z= 60, A=144), MT= 28 (n,np)
Nd-144 (Z= 60, A=144), MT=104 (n,d)
Nd-145 (Z= 60, A=145), MT= 32 (n,nd)
Nd-145 (Z= 60, A=145), MT= 41 (n,2np)
Nd-145 (Z= 60, A=145), MT=105 (n,t)
Nd-146 (Z= 60, A=146), MT= 33 (n,nt)
Pm-147 (Z= 61, A=147), MT= 22 (n,nα)
Pm-148 (Z= 61, A=148), MT= 24 (n,2nα)
Pm-148 (Z= 61, A=148), 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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Pr-143 U-235 Thermal 4.492840e-09 2.875420e-09
Pr-143 U-235 Fast 1.606690e-09 1.028280e-09
Pr-143 U-235 High 3.995480e-06 2.557100e-06
Pr-143 U-238 Fast 6.362370e-11 4.071920e-11
Pr-143 U-238 High 1.231350e-08 7.880580e-09
Pr-143 Pu-239 Thermal 3.359470e-07 2.150060e-07
Pr-143 Pu-239 Fast 3.549430e-07 2.271630e-07
Pr-143 Pu-239 High 3.860500e-05 2.470720e-05
Pr-143 Pu-241 Thermal 1.910310e-09 1.222600e-09
Pr-143 Pu-241 Fast 4.256800e-09 2.724350e-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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Pr-143 U-235 Thermal 5.947850e-02 4.243420e-04
Pr-143 U-235 Fast 5.721970e-02 5.804300e-04
Pr-143 U-235 High 3.821190e-02 1.069950e-03
Pr-143 U-238 Fast 4.632000e-02 4.727140e-04
Pr-143 U-238 High 3.917170e-02 7.863460e-04
Pr-143 Pu-239 Thermal 4.412790e-02 4.413410e-04
Pr-143 Pu-239 Fast 4.341530e-02 2.171330e-04
Pr-143 Pu-239 High 2.809710e-02 1.684800e-03
Pr-143 Pu-241 Thermal 4.581110e-02 6.416760e-04
Pr-143 Pu-241 Fast 4.669970e-02 9.343330e-04
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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