59-Pr-142
Spin
Level energy(keV) Spin & Parity
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ground state 2-
3.68300E+00 5-
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)
141.910049607 ± 0.000002291 (amu) [mass excess = -83788.251 ± 2.135 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2161.635 ± 1.487 (keV)
Strong Gamma-rays from Decay of Pr-142 (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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642.0 2.E-03 EC
508.8 0.02 B-
1575.6 3.68 B-
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86.7 -- IT
268.2 -- IT
553.0 -- 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- 19.12 H 4
EC 19.12 H 4
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Pr-141 (Z= 59, A=141), MT=102 (n,γ)
Pr-143 (Z= 59, A=143), MT= 16 (n,2n)
Nd-142 (Z= 60, A=142), MT=103 (n,p)
Nd-143 (Z= 60, A=143), MT= 28 (n,np)
Nd-143 (Z= 60, A=143), MT=104 (n,d)
Nd-144 (Z= 60, A=144), MT= 32 (n,nd)
Nd-144 (Z= 60, A=144), MT= 41 (n,2np)
Nd-144 (Z= 60, A=144), MT=105 (n,t)
Nd-145 (Z= 60, A=145), MT= 33 (n,nt)
Pm-147 (Z= 61, A=147), 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-142 U-235 Thermal 1.382170e-11 8.845910e-12
Pr-142 U-235 Fast 4.198930e-12 2.687320e-12
Pr-142 U-235 High 5.509960e-08 3.526370e-08
Pr-142 U-238 Fast 2.000020e-13 1.280020e-13
Pr-142 U-238 High 8.316960e-11 5.322870e-11
Pr-142 Pu-239 Thermal 3.258580e-09 2.085500e-09
Pr-142 Pu-239 Fast 3.108300e-09 1.989310e-09
Pr-142 Pu-239 High 9.309440e-07 5.958040e-07
Pr-142 Pu-241 Thermal 8.193930e-12 5.244110e-12
Pr-142 Pu-241 Fast 1.518420e-11 9.717880e-12
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Pr-142m U-235 Thermal 3.240470e-11 2.073910e-11
Pr-142m U-235 Fast 1.146870e-11 7.339990e-12
Pr-142m U-235 High 2.493180e-07 1.595630e-07
Pr-142m U-238 Fast 5.462750e-13 3.496170e-13
Pr-142m U-238 High 3.763310e-10 2.408520e-10
Pr-142m Pu-239 Thermal 7.639690e-09 4.889410e-09
Pr-142m Pu-239 Fast 8.489830e-09 5.433480e-09
Pr-142m Pu-239 High 4.212390e-06 2.695930e-06
Pr-142m Pu-241 Thermal 1.921050e-11 1.229470e-11
Pr-142m Pu-241 Fast 4.147320e-11 2.654290e-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)
-----------------------------------------------------------
Pr-142 U-235 Thermal 4.622650e-11 2.541190e-11
Pr-142 U-235 Fast 1.566770e-11 8.519500e-12
Pr-142 U-235 High 3.044180e-07 1.644420e-07
Pr-142 U-238 Fast 7.462770e-13 4.055860e-13
Pr-142 U-238 High 4.595000e-10 2.482060e-10
Pr-142 Pu-239 Thermal 1.089830e-08 5.988290e-09
Pr-142 Pu-239 Fast 1.159810e-08 6.304030e-09
Pr-142 Pu-239 High 5.143340e-06 2.778130e-06
Pr-142 Pu-241 Thermal 2.740440e-11 1.505640e-11
Pr-142 Pu-241 Fast 5.665740e-11 3.079950e-11
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Pr-142m U-235 Thermal 3.240470e-11 2.073910e-11
Pr-142m U-235 Fast 1.146870e-11 7.339990e-12
Pr-142m U-235 High 2.493180e-07 1.593270e-07
Pr-142m U-238 Fast 5.462750e-13 3.494890e-13
Pr-142m U-238 High 3.763310e-10 2.405910e-10
Pr-142m Pu-239 Thermal 7.639690e-09 4.889410e-09
Pr-142m Pu-239 Fast 8.489830e-09 5.433480e-09
Pr-142m Pu-239 High 4.212390e-06 2.694180e-06
Pr-142m Pu-241 Thermal 1.921050e-11 1.229270e-11
Pr-142m Pu-241 Fast 4.147320e-11 2.654290e-11
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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