59-Pr-144
Spin
Level energy(keV) Spin & Parity
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ground state 0-
5.90300E+01 3-
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)
143.913310859 ± 0.000003233 (amu) [mass excess = -80750.415 ± 3.012 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2997.440 ± 2.400 (keV)
Strong Gamma-rays from Decay of Pr-144 (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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59.03 -- IT
617.8 0.02 B-
1631.36 0.03 B-
1885.3 0.01 B-
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696.51 1.34 B-
1489.16 0.28 B-
2185.66 0.69 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- 17.28 M 5
B- 7.2 M 3
IT 7.2 M 3
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Pr-143 (Z= 59, A=143), MT=102 (n,γ)
Nd-144 (Z= 60, A=144), MT=103 (n,p)
Nd-145 (Z= 60, A=145), MT= 28 (n,np)
Nd-145 (Z= 60, A=145), MT=104 (n,d)
Nd-146 (Z= 60, A=146), MT= 32 (n,nd)
Nd-146 (Z= 60, A=146), MT=105 (n,t)
Nd-147 (Z= 60, A=147), MT= 33 (n,nt)
Pm-147 (Z= 61, A=147), MT=107 (n,α)
Pm-148 (Z= 61, A=148), MT= 22 (n,nα)
Pm-148 (Z= 61, A=148), MT= 22 (n,nα)
Pm-149 (Z= 61, A=149), 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-144 U-235 Thermal 1.434950e-08 9.183640e-09
Pr-144 U-235 Fast 4.743700e-09 3.035960e-09
Pr-144 U-235 High 2.013620e-06 1.288720e-06
Pr-144 U-238 Fast 2.964810e-10 1.897470e-10
Pr-144 U-238 High 1.920730e-08 1.229270e-08
Pr-144 Pu-239 Thermal 3.691980e-07 2.362870e-07
Pr-144 Pu-239 Fast 5.045480e-07 3.229110e-07
Pr-144 Pu-239 High 1.396100e-05 8.935010e-06
Pr-144 Pu-241 Thermal 7.834820e-09 5.014290e-09
Pr-144 Pu-241 Fast 1.349120e-08 8.634340e-09
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Pr-144m U-235 Thermal 1.277240e-07 8.174360e-08
Pr-144m U-235 Fast 4.855630e-08 3.107600e-08
Pr-144m U-235 High 3.270400e-05 2.093050e-05
Pr-144m U-238 Fast 3.034760e-09 1.942240e-09
Pr-144m U-238 High 3.119530e-07 1.996500e-07
Pr-144m Pu-239 Thermal 3.286230e-06 2.103180e-06
Pr-144m Pu-239 Fast 5.164530e-06 3.305300e-06
Pr-144m Pu-239 High 2.267450e-04 1.451170e-04
Pr-144m Pu-241 Thermal 6.973760e-08 4.463220e-08
Pr-144m Pu-241 Fast 1.380950e-07 8.838070e-08
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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-144 U-235 Thermal 5.491350e-02 2.869830e-04
Pr-144 U-235 Fast 5.278490e-02 5.359990e-04
Pr-144 U-235 High 3.176830e-02 8.894500e-04
Pr-144 U-238 Fast 4.554210e-02 4.590730e-04
Pr-144 U-238 High 3.728310e-02 1.043830e-03
Pr-144 Pu-239 Thermal 3.739180e-02 1.870680e-04
Pr-144 Pu-239 Fast 3.672330e-02 2.571580e-04
Pr-144 Pu-239 High 2.706040e-02 1.081850e-03
Pr-144 Pu-241 Thermal 4.228500e-02 4.228890e-04
Pr-144 Pu-241 Fast 4.168320e-02 1.668660e-03
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Pr-144m U-235 Thermal 8.293280e-04 5.805270e-06
Pr-144m U-235 Fast 7.971090e-04 1.115950e-05
Pr-144m U-235 High 5.118870e-04 3.237970e-04
Pr-144m U-238 Fast 6.876960e-04 9.627770e-06
Pr-144m U-238 High 5.632870e-04 1.577200e-05
Pr-144m Pu-239 Thermal 5.678530e-04 1.589980e-05
Pr-144m Pu-239 Fast 5.596060e-04 1.566890e-05
Pr-144m Pu-239 High 6.317290e-04 3.560480e-04
Pr-144m Pu-241 Thermal 6.385790e-04 6.385790e-06
Pr-144m Pu-241 Fast 6.295600e-04 3.777360e-05
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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